Letter Sequence Draft 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 1.2
[ .EOP-0 Deviation Document 4 DRAFT #1 04-01-84 ,
~EOP-0 REACTOR TRIP OR SAFETY INJECTION 5
-REFERENCE DOCUMENTS WOG Procedure E-0, LP-Rev. 1 PBNP Procedure EOP-0, Draft #1, 04-01-84 COVER PAGE s
The purpose section was reworded to provide a more explicit description of how the procedure is used. ,
The symptoms or entry conditions section was reduced in content. This was done because some of the information in the generic procedure is knowledge that we expect our operators to have and doesn't need to be in the procedure. It was
' also felt that the section in the generic procedure was more wordy than necessary and the plant section was written to alleviate this.
NOTE PRIOR TO STEP 1 - (WOG 1)
The first note was changed to include key words following the step number to be
- .used by the operator as additional verification that the step numbers are correct. .This is also explained in the Emergency Operating Procedure Writer's Guide.
3 -NOTE PRIOR TO STEP 1 - (-)
The second note was added to direct the operator to additional instructions if a loss of.offsite AC power has occurred. The Westinghouse Owners' Group did not cddress this concern in the generic procedure due to the plant specific nature.
NOTE PRIOR TO STEP 1 - (WOG 1)
Same
. NOTE PRIOR TO STEP 1 - (-) ,
The fourth note was added to ensure the proper notifications are made.
8406060214 840601 '
. ..PDR ADOCK 05000266
-F PDR- .
I s.
E0P-0 Deviation Document Page 2 STEP 1 - (WOG 1) l The plant step does not refer to reactor trip bypass breakers because they are nst conveniently located for the operator in the control room. The procsdure transfer does not specifically reference Step.1 since it is implicitly understood to go to the start of the procedure if no step number is indicated.
This is intended to avoid unnecessary clutter in the procedure and will be Emphasized during operator training.
STEP 2 - (WOG 2)
The word "all" was not included since there are only two and the word valves is sufficient.
STEP 3 - (WOG 3)
This step was reworded to include plant specific terminology and reduce the verbiage. The information content is equivalent to the generic step.
STEP 4 - (WOG 4)
Same STEP 5 - (-)
+ This step verifies the Diesels have activated. This step was present in previous plant emergency operating procedures and is important enough to be included here.
STEP 6 - (WOG 5)
This step was reworded to include plant specific terminology. The plant doe, not have feedwater isolation valves or sample valves that go shut upon a safety injection signal and these steps are not included in the plant procedure.
STEP 7 - (WOG 6) .
The plant has only one type of containment isolation signal and thus the phrase Phase A is not appropriate. This step was expanded to include some local cetions that may need to be performed.
STEP 8 - (WOG 7) d
-The substeps are unnecessary because the high level step is sufficiently clear.
y g p,-<- . --- m-- , ,-- , e-,-- + , - - - ,
4 E0P-0 4 Deviation Document Page 3 1
STEP 9 - (WOG 8)
STEP 10 - (WOG 8)
The generic step was made into two high level steps to make it more consistent with adjacent steps.
STEP 11 - (WOG 10)
The step has expanded to check if nonessential service water isolation has occurred.
STEP 12 - (WOG 11)
Plant specific terminology was used.
STEP 13 - (-)
This step checks for proper Diesel loading. It was present in past versions of the plant emergency operating procedures and is important enough to be included hare. This step along with Steps 14, 15 & 16 are plant specific steps allowed for by the note prior to Step 13 of the generic procedure.
STEP 14 - (-)
This step checks that the turbine does not motor and cause damage. It was present in past versions of the plant emergency operating procedures and is important enough to be included here.
STEP 15 - (-)
This step ensures proper continuation of electrical power. It was present in past versions of the plant emergency operating procedures and is important Gnought to be included here.
-STEP 16 - (-)
This step verifies that certain safeguards actuated valves operate properly. It was present in past versions of the plant emergency operating procedures and is important enough to be included here.
STEP 17 - (WOG 13)
The plant step was reworded because it was felt the generic step was ambiguous.
f
E0P-0 Deviation Document 4 Page 4 STEP 18 - (WOG 14)
This step was reworded to allow additional plant specific instructions to be included. The reactor coolant pumps are not tripped because there is still component cooling water flow to the motors following a containment isolation 5
etntrary to the generic plant design.
NOTE PRIOR TO STEP 19 - (-)
This note prevents'the isolation of an unfaulted safety injection flow path.
It was present in past versions of the emergency operating procedures and is important enough to be included here.
STEP 19 - (WOG 15)
Plant specific terminology and a simplification of the generic wording was ured. ,
STEP 20 - (-)
This is a plant specific step to ensure water flows to the affected unit.
It is needed due to this being a two unit site.
STEP 21 - (WOG 16)
The wording of the generic step was changed slightly.
STEP 22 - (WOG 9)
This step was moved to a later time in the plant procedure than in the generic procedure because it is not as critical as some of the other steps.
STEP 23 .(WOG 19)
Some slight changes were made to make the step fit the plant procedure format cnd more accurately describe the reactor coolant pump trip criteria.
STEP 24 - (WOG 20)
Some slight changes were made to make the step fit the plant procedure format.
CAUTION PRIOR TO STEP 25 - (WOG 33 & 19)
Same
EOP-0
& Deviation Document Page 5 NOTE PRIOR TO STEP 25 - (-) ,
l This note reminds the operator that he may need to manually activate safety l injection equipment. It was present in past versions of the emergency operating procedures and is important enough to be included here. 3 STEP 25'- (WOG 33)
This step was moved to earlier in the plant procedure than in the generic to allow for reestablishing instrument air to containment. Resetting safety injection does not cause any automatic actions to take place.
CAUTION PRIOR TO STEP 26 - (-)
This caution was added to ensure the Duty Shift Superintendent is made aware of
&ctions the operator may make to defeat containment isolation.
STEP 26 -(WOG 34)
This step was moved up to keep it with the previous step. There is only one type of containment isolation and the words Phase A are not needed.
CAUTION PRIOR TO STEP 27 - (-)
This is additional instructions to prevent loss cf instrument air pressure. It was present in past versions of the emergency operating procedures and is necessary due to this being a two unit site.
STEP 27 - (WOG 35)
This step was moved up to allow operation of equipment inside containment sarlier in the recovery. Some plant specific instructions are included.
STEP 28 - (WOG 21)
This step was changed to make it more general and also similar to steps in other generic emergency procedures. The information that is checked is the same between the plant and generic procedure.
STEP 29 - (WOG 22)
Same STEP 30 - (WOG 23)
This step was reworded to avoid using negative statements.
EOP-0
-s Deviation Document Page 6 STEP 31 - (WOG 24)
This step was reworded to avoid using the word normal.
STEP 32 - (WOG 25) ,
This step was reworded to avoid using the word normal.
STEP 33 - (WOG 26)
The wording was changed slightly based upon desires of plant Staff.
STEP 34 - (WOG 27)
Same STEP 35 - (WOG 28)
Same CAUTION PRIOR TO STEP 36 - (WOG 29)
The caution was rewordad to keep the conoition prior to the action. The word will was changed to may to give.the operator more freedom to determine the best cause of action as several options are available.
STEP 36 - (WOG 29)
The generic step appeared. redundant and overly complicated. 7he step was reworded to alleviate this.
STEP 37 - (WOG 30)
The high level step was reworded to avoid using the word normal.
STEP 38 - (WOG 31)
The high level step was reworded to avoid using the word normal.
STEP 39 - (WOG 32)
The high level step was reworded to avoid using the word normal.
CAUTION PRIOR TO STEP 40 - (WOG 36)
The caution was shortened to remove a statement from the generic procedure that is not needed due to operator training.
i
E0P-0 Deviation Document Page 7 STEP 40 - (WOG 36)
The step was reworded slightly to be more consistent with our plant specific fermat. All of the information in the generic step is retained in the plant step.
STEP 41 - (-)
This caution was included to control loading on the emergency Diesel g:nerators. It was present in past versions of the emergency operating procedures and is important enough to be included here.
STEP 42 - (WOG 37)
This step was reorganized to be consistent with the plant method of addressing loss of offsite AC power concerns.
NOTE PRIOR TO STEP 43 - (-)
This note was included to alert the operator that he has lost letdown along with the charging pumps. This information was present in past versions of the cmergency operating procedures and is important enough to be included here.
STEP 43 - (WOG 38)
This high level step was reworded to show that charging flow has probably not been lost.
STEP 44 - (WOG 39)
Part of the intent of the generic step is included in Step 41 of the plant procedure. The instruction to restore offsite AC is unnecessary because it is cn obvious action that operators would do based on their training.
STEP 45 - (WOG 40)
Same i
L ..
o EOP-0 Deviation Document Page 8 ITEMS OF THE GENERIC PROCEDURE THAT ARE NOT INCLUDED IN THE PLANT PROCEDURE Step 12 of the generic procedure verifies containment ventilation isolation.
These valves are checked in Step 7a of the plant procedure that verifies centainment isolation. For this reason the generic step is not needed in5 the plant procedure.
Step 17 & 18 of the generic procedure verify proper valve alignment for safety injection and auxiliary feedwater. The operator has already verified that these pumps are running and flow indication is present. The steps to verify valve alignment are not necessary due to these previous checks and the general operator training. When an operator checks for flow he would also check for some indication that it is going where he expects.
A caution prior to Step 19 of the generic procedure referring to loss of offsite AC is not needed in the same place in the plant procedure because the plant step does not reset safety injection.
A caution prior to Steps 19 & 33 of the generic procedure referring to safety injection pump suction is not necessary because the automatic pump suction transfer does not depend on a safety injection signal in any way.
.
