Letter Sequence Other |
|---|
|
|
MONTHYEARML20091J8441983-09-0101 September 1983
Rev 1 to Emergency Operating Procedure E-0, Reactor Trip or Safety Injection
Project stage: Other
ML20091J8561984-02-21021 February 1984
Emergency Operating Procedure Verification Procedure
Project stage: Other
ML20091J8371984-04-0101 April 1984
Deviation Document,Draft 1 to Emergency Operating Procedure EOP-0, Reactor Trip or Safety Injection
Project stage: Draft Other
ML20091J8281984-04-0101 April 1984
Draft 1 to Emergency Operating Procedure EOP-0, Reactor Trip of Safety Injection
Project stage: Draft Other
ML20091J8581984-05-23023 May 1984
Emergency Operating Procedure Validation Procedure
Project stage: Other
ML20091J8491984-06-0101 June 1984
Rev 0 to Emergnecy Operating Procedure Pbnp 4.19, Emergency Operating Procedure Writers Guide
Project stage: Other
ML20091J8181984-06-0101 June 1984
Forwards Addl Info on Generic Ltr 82-33,Suppl 1 to NUREG-0737 Re Procedure Generation Package Upgraded Emergency Operating Procedures
Project stage: Other
ML20100K6901984-12-0606 December 1984
Responds to 841109 Request for Addl Info Re Implementation of Emergency Operating Procedures.Mod of Existing Procedures,Addition of Interim Procedures & Verification/ Validation Process Discussed
Project stage: Request
ML20101A2141984-12-12012 December 1984
Notifies That Util Unable to Complete Item 5A of 840703 Confirmatory Order by Dec 1984 Schedule Due to Vendor Inability to Deliver Automatic Bus Transfer Switch.Requests Item 5A Be Changed to Indicate Completion by 850121
Project stage: Other
1984-02-21
[Table View] |
|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999
Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs
ML20210M6171999-08-0404 August 1999
Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys
ML20210B5121999-07-15015 July 1999
Pbnp Simulator Four-Yr Rept
ML20209C1831999-07-0101 July 1999
Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS
ML20205R6741999-04-12012 April 1999
Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR
ML20203A2261999-02-0202 February 1999
Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design
ML20202F6521999-01-29029 January 1999
Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes
ML20154G5601998-10-0707 October 1998
Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility
ML20154H4231998-10-0505 October 1998
Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis
ML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20154C1941998-09-28028 September 1998
Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels
ML20153G7361998-09-23023 September 1998
Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers)
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20236W7861998-07-30030 July 1998
Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability
ML20249C3811998-06-22022 June 1998
Proposed Corrected Tech Specs Pages Re Radiological Effluents
ML20248C6651998-05-28028 May 1998
Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses
ML20248G1671998-05-27027 May 1998
Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1
ML20203K9571998-02-26026 February 1998
Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12
ML20203K2981997-12-15015 December 1997
Proposed Tech Specs Re Administrative Controls
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20247P2681997-09-23023 September 1997
Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles
ML20210M5151997-08-14014 August 1997
Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test
ML20210J0331997-08-0707 August 1997
Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording
ML20140C9111997-06-0303 June 1997
Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1
ML20141C5931997-05-0909 May 1997
Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140D7251997-04-14014 April 1997
Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c
ML20140D7091997-04-14014 April 1997
Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20137N6451997-04-0202 April 1997
Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20137C8331997-03-20020 March 1997
Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
ML20137P8441997-02-14014 February 1997
Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews)
ML20140G9351997-02-14014 February 1997
Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling)
ML20140G8921997-02-14014 February 1997
Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown)
ML20140G9401997-02-0707 February 1997
Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing
ML20138K2991997-01-31031 January 1997
Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory
ML20138K2031997-01-31031 January 1997
Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1
ML20138K2551997-01-31031 January 1997
Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1
ML20138K2411997-01-31031 January 1997
Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1
ML20138K3231997-01-31031 January 1997
Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode)
ML20137P8551997-01-31031 January 1997
Brine Tank Standpipe Mod
ML20138K3071997-01-31031 January 1997
Rev 38 to OP 9C, Containment Venting & Purging
ML20138K2901997-01-31031 January 1997
Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2
ML20138K2641997-01-31031 January 1997
Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2
ML20138K4991997-01-31031 January 1997
Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2
ML20138K3181997-01-31031 January 1997
Rev 33 to RP 1B, Recovery from Refueling
ML20138K3031997-01-31031 January 1997
Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes
ML20138K2251997-01-31031 January 1997
Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2
ML20138K4791997-01-31031 January 1997
Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1
ML20138K4701997-01-31031 January 1997
Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1
ML20138K5041997-01-31031 January 1997
Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2
ML20138K5161997-01-31031 January 1997
Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2
ML20138K4751997-01-31031 January 1997
Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1
ML20138K5231997-01-31031 January 1997
Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2
ML20138K7311997-01-31031 January 1997
Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly)
ML20138K7171997-01-31031 January 1997
Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1
ML20138K3121997-01-31031 January 1997
Rev 43 to RP 1A, Preparation for Refueling
1998-09-30
[Table view] |
Text
'
, ATTACHMENT 1.3 i
. 'n n m .. ja.,a o. ,
' #'"'" I E.0 REACTOR TRIP OR SAFETY INJECTION
, 1 Sept.1983 A. PURPOSE This guideline provides actions to verify proper response of the automatic protection systems
~
following manual or automatic actuation of a reactor trip or safety injection, to sssess plant conditions, and to identify the appropriate recovery guideline.
B. 5YMPTOMS OR ENTRY CONDITIONS
- 1) The following are symptoms that require a reactor trip, if one has not occurred:
[ Enter plant specific setpoints and requirements).
- 2) The following are symptoms of a reactor trip: ,
- c. Any reactor trip annunciator lit,
- b. Rapid decrease in neutron level indicated by nuclear instrumentation.
- c. All shutdown and control ror's are fully inserted. Rod bottom lights are lit.
- 3) The following are symptoms that require a reactor trip and safety injection, if one hos not occurred:
[ Enter plant specific setpoints and requirements). 1
- 4) The following are symptoms of a reactor trip and safety injection:
- a. Any Si annunciator lit.
- b. Si pumps running.
- c. [ Enter plant specific list].
t e
~
8406060220 840601 PDR ADOCK 05000266 F PDR
s LP Rev. I E0 REACTOR TRIP OR SAFETY INJECTION 1 Sept.1983 J
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
NOTE
- Steps 1 through 14 are IMMEDIA TE ACTION steps.
~
- Foldout page should be open. ,
i 1 Verify Reector Trip: Manually trip reactor. E reactor will NOT ,
i trip, THEN go to FR-5.1, RESPONSE TO
- Rod bottom lights - LIT NUCLEAR POWER GENERATION / ATWS,
OPEN St'P I-
- Rod position indicators - AT ZERO
- Neutron flux - DECREASING 2 Verify Turbine Trip:
- a. All turbine stop volves - CLOSED o. Manually trip turbine.
3 Verify Power To AC Emergency Busses:
- a. AC emergency busses - AT LEAST o. Try to restore power to at least one ONE ENERGl2ED oc emergency bus.E power con NOT be restored to at least one ac emergency bus, THEN go to ECA-0.0, LOSS OF ALL AC POWER, Step 1.
- b. AC emergency busses - ALL b. Try to restore power to deenergized ENERGlZED oc emergency busses.
4 Check if Si is Actuated: Check if 51 is required. 2 51 is required.
THEN manually actuate. 2 Si is NOT
[ Enter plant specific means]
required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.
t 2 of 13
- rm., i. n . ,w, LP Rev. 1 E0 REACTOR TRIP OR SAFETY INJECTION
. 1 Sept.1983 I
STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
5 Verify FW isolation: Manually close valves as necessary.
- Flow control valves - CLOSED
-
- Flow control bypass valves - CLOSED
- FW isolation volves - CLOSED
- SG blowdown isolation valves -
CLOSED
+ SG sample isolation volves - CLOSED 6 Verify Containment Isolation Phase A:
- a. Phase A - ACTUATED a. Manually actuate Phase A.
- b. Phase A valves - CLOSED b. Manually close valves.
7 Verify AFW Pumps Running:
- a. MD pumps - RUNNING a. Manually start pumps.
- b. Turbine-driven pump - RUNNING IF b. Manually open steam supply valves NECESSARY 8 Verify $l Pseps Running: Manually start pumps.
- High-head 51 pumps - RUNNING
- Low-head Si pumps - RUNNING 9 Verify CCW Pumps - RUNNING Manually start pumps.
3 ef 13 i.
I _. _.. .. _ . _ .
iMonsters TH6es lRev. leave /Deses l
E0 LP-Rev.1 REACTOR TRIP OR SAFETY INJECTION 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
10 Verify Service Water Pumps - RUNNING Manually start pumps.
11 Verify Containment Fon Coolers - Manually start fan coolers in emergency
_ RUNNING IN EMERGENCY MODE mode.
12 Verify Containment Ventikion Isolation:
- a. Dampers - CLOSED o. Manually close dampers.
(Appropriate steps for verification of other essential equipment as required by the specific plant design should be p! aced after Step 12.]
13 Check if Main Steomlines should Be Isolated:
- a. [ Enter plant specific means or a. Go to Step 14.
setpoints]
- b. Verify main steamline isciation and b. Manually close volves, bypass valves - CLOSED ,
14 Verify Containment Spray Not Required:
- a. Containment pressure - HAS a. Perform the following:
REMAINED LESS THAN u) PSIG 1) Verify containment spray initiated.
jf NQ.T, THEN manually initiate.
- 2) Verify containment isolation Phase B volves closed g NJ, THEN manually close volves.
- 3) Stop all RCPs.
l 4 of 13
!~
- psewed art flese: Rev. leave /Deses E0
l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
15 Verify 51 Flow:
- a. RCS pressure - LESS THAN (2) PSIG o. Ga to Step 16.
((J) PSIG FOR ADVERSE CONTAINMENT]
- b. High-head 51 pump flaw indicators - b. Manually start pumps and align CHECK FOR FLOW valves.
- c. RCS pressure - LESS THAN (4) PSIG c.' Go to Step 16.
[($) PSIG FOR ADVER5E CONTAINMENT]
- d. Law-head 51 pump f!aw indicatars - d. Manually start pumps and align CHECK FOR FLOW volves.
16 Verify AFW Flow - GREATER THAN Manually start pumps and align valves as (6) GPM necessary. IF AFW flaw greater than (6/ gpm can NOT be established, THEN ga to FR H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.
17 Verify AFW Velve Alignment - PROPER Manually align volves as necessary.
EMERGENCY ALIGNMENT 18 Verify SI Velve Alignment - PROPER Manually align volves as necessary.
EMERGENCY ALIGNMENT l
l I
l 5 si13 i
i
Asv. leave @ eve:
[habert TMos LP Rev. 1
- E0 REACTOR TRIP OR SAFETY INJECTION
STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED CA UTION
- If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
- If SIis reset before automatic transfer of high-head SIpump suction to RWST occurs, manual transfer on BA T low level is required.
19 Check RCP Seal Cooling:
- a. CCW flow to RCP thermal barriers - c. E CCW to an RCP is lost, THEN:
NORMAL 1) Trip the RCP.
- 2) Reset 51.
- 3) Verify adequate power available to run one charging pump. If necessary, shed sufficient non-essential loads.
- 4) Start one charging pump at minimum speed for soci injection.
20 Check RCS Average Temperature - E temperature less than (7;*F ond STABLE AT OR TRENDING TO (7;*F decreasing, THEN:
a) Stop dumping steam.
b) { cooldown continues, THEN control total feed flow. Maintain total feed
> flow greater than (6i gpm until narrow range level grecter than /31%
(t91% for adverse containment) in at least one SG.
c) { cooldown' continues, THEN close main steamline isolation and bypass valves.
g temperature greater than (7)*F and increasing, THEN: ,
-OR-
6 of 13
n*n m ,a . mm ,
~
E0 REACTOR TRIP OR SAFETY INJECTION LP Rev. 1 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
l 21 Check PRZR PORVs And Spray Volves:
- o. PORVs - CLOSED o. E PRZR pressure le'ss than /101 psig, THEN manually close PORVs.E any volve con NOT be closed, THEN manually close its block valve. E block volve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDA#Y COOLANT, Step 1.
- b. Normal FRZR spray valves - CLOSED b. IF /RZR preseare less then //11 psig, THEN manually lose valves. IFF valves can NOT be closed. THEN stop RCP(s).
supplying failed spray cive(s).
22 Check If RCPs should Be Stopped:
- a. High-head 51 pumps - AT LEAST o. Go to Step 23.
ONE RUNNING
- b. RCP Trip Parameter - LESS THAN //11 b. Go to Step 23.
[(1.7) FOR ADVERSE CONTAINMENT]
- c. Stop oil RCPs i
l l
l l
7 of 13
mn m .. I a .i ,
REACTOR TRIP OR SAFETY INJECTION LPcRev.1 E0 1 Sept.1983 )
STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
I 23 Check if SGs Are Not Fowlted:
- a. Check pressures in all SGs - a. Go to E-2, FAULTED STEAM GENERATOR 150LAT40N, Step 1.
- NO SG PRESSURE DECREASING IN AN UNCONTROLLCD MANNER
- NO SG COMPLETELY DEPRESSURIZED 24 Check if SG Tubes Are Net Ruptured: Go to E-3, STEAM GENERATOR TUBE
- Condenser air ejector radiation - RUPTURE, Step 1.
NORMAL
- SG blowdown radiation - NORMAL 25 Check if RCS is latect: Go to E 1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- Containment radiction - NORMAL
- Containment pressure - NORMAL
- Containment recirculation sump level - NORMAL 8 of 13 l
w m. ja .i ,
REACTOR TRIP OR SAFETY INJECTION LP Rev. 1 E0 1 Sept.1983 d STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If 51 Flow Should Be Terminated:
- o. RCS subcooling based on core exit a. DO NOT STOP 51 PUMPS. Go to
~
TCs - GREATER THAN (14;*F Step 28.
- b. Secondary heat sink: b. E neither condition satisfied, THEN DO NOT STOP 51 PUMPS. Go to
- Total feed flow to SGs - GREATER Step 28.
THAN (6) GPM
-OR-
- Narrow range level in at least one SG - GREATER THAN /3/%
- c. RCS pressure: c. DO NOT STOP 51 PUMPS. Go to Step 28.
- Pressure - GREATER THAN (2) PSIG
- Pressure - STABLE OR INCREASING
- d. PRZR level - GREATER THAN (15>% d. DO NOT STOP 51 PUMPS. Try to stabilize RCS pressure with normal PRIR spray. Return to Step 260.
27 Go To E51.1, $1 TERMINATION, Step 1 l
l l
9 of 13
Muh fl8088 Rev. lanes */ Deco:
LP Rev. 1 E0 REACTOR TRIP OR SAFITY INJECTION i
1 hpt.1983 STEP l ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
28 laitiste Monitoring Of Critical Sofety Function Status Trees ,
CA UTION Alternate water sourcesfor AFWpumps will be necessary if CST level decreases to less than n6).
29 Geck SG Levels:
- a. Narrow range level - GREATER THAN a. Maintain total feed flow greater than (81% (6) gpm until narrow range level greater than ts)% in at least one SG.
- b. Control feed flow to maintain narrow b. IF narrow rsage level in any SG range level between ts>% and 50% continues to increase in an uncontrolled manner, THEN go to E 3, l
STEAM GENERATOR TUBE RUPTURE, Step 1.
30 Deck Secondary Rodietion - NORMAL Go to E 3, STEAM GENERATOR TUBE RUPTURE, Step 1.
[ Enter plant specific means]
31 Geck Auxiliory Building Redietion - Evaluate cause of abnormal conditions. LF .
NORMAL the cause is o loss of RCS inventory outside containment, THEN go to ECA 1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
t 32 Geck PRT Conditions - NORMAL Evoluote cause of abnormal conditions.
en 10 of 13 y - ,, -- - - . , --- , - , , , , -------,.a , ,- , -- ,-- -
IW TMet Sov. leave / Dees LP Rev. I
> E.0 REACTOR TRIP OR SAFITY INJECTION 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED I
CA UTION
- If offsite power is lost after SI reset, jnanua!
action may be required to restart safeguards equipment.
- If SIis reset before automatic transfer of high-head SIpump suction to RWST occurs, manual transfer on BA T low level is required.
33 Reset 51 34 Roset Containment Isolation Phase A And Phase B 35 Establish lastrument Air To Conteinment Start one air compressor and establish instrument air to containment.
CA UTION RCS pressure should be monitored. If RCS pressure decreases to less than u> psig the low-head SI
- pumps must be manually restarted to supply water to the RCS.
36 Check If Lew.ifeed $1 Pumps Shevid Be Stopped:
- a. Check RCS pressure:
- 1) Pressure - GREATER THAN 1) Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
(4) PSIG
- 2) Pressure - STABLE OR INCREASING 2) Go to Step 37.
- b. Stop low head 51 pumps and place in stondby li d 13
. , . - , .. . , - . , . _ . . . ~ , - - _ , , , - , - . , - - . . , , , -
Tmeen m es n .wm REACTOR TRIP OR SAFETY INJECTION 1.P.Rev.1 E0 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
37 Oeck Power Supply To Gorging Verify adequate diesel capacity to run Pomps - 0FFSITE POWER AVAILABLE charging pumps. If necessary, shed
~
sufficient non-essential loads.
38 Geck if Charging Flow Has Been Established:
- a. Charging pumps - AT LEAST ONE o. Perform the following:
RUNNING 1) 1F CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(5) before starting charging pumps.
- 2) Start charging pumps as necessary.
- b. Establish flow as 'necessary:
[ Enter plant specific means]
39 Geck if Diesel Generators 5hecid Be Stepped:
- a. Verify oc emergency busses - c. Try to restore offsite power to oc ENERGlZED BY OFFSITE POWER emergency busses.2 offsite power con NOT be restored, THEN loo.1 the following equipment on ac emergency busses:
(Enter piant specific list).
- b. Stop any unloaded diesel generator and place in standby 40 Return Te Step 20 .
- END -
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