Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5171999-08-25025 August 1999
Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A4961999-08-23023 August 1999
Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys.
ML18107A4671999-07-29029 July 1999
Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4601999-07-23023 July 1999
Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4241999-07-0202 July 1999
Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR
ML18107A3811999-06-10010 June 1999
Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3601999-06-0404 June 1999
Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML18107A2131999-04-14014 April 1999
Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431
ML18106B1591999-03-31031 March 1999
Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
ML18106B0801999-02-22022 February 1999
Proposed Tech Specs Re CR Emergency Air Conditioning Sys
ML18106B0641999-02-0808 February 1999
Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing
ML18106B0611999-02-0808 February 1999
Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions.
ML18106B0531999-02-0202 February 1999
Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel
ML18106B0431999-01-19019 January 1999
Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys
ML18106B0241999-01-15015 January 1999
Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
ML18106A9231998-10-12012 October 1998
Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03
ML18106A9181998-10-12012 October 1998
Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10
ML18106A8941998-09-29029 September 1998
Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
ML18106A8781998-09-17017 September 1998
Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity
ML18106A8371998-08-12012 August 1998
Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door
ML18106A7931998-07-30030 July 1998
Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase
ML18106A6961998-07-0707 July 1998
Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan
ML18106A6631998-06-17017 June 1998
Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A4241998-03-26026 March 1998
Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A4291998-03-26026 March 1998
Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18106A3221998-02-18018 February 1998
Marked-up TS Pages for Section 4.2.1 of App B
ML18106A3091998-02-0202 February 1998
Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation
ML18106A2541998-01-0808 January 1998
Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2141997-12-15015 December 1997
Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1961997-12-11011 December 1997
Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6791997-11-14014 November 1997
Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6751997-11-14014 November 1997
Proposed Tech Specs Re Administrative & Editorial Corrections
ML18102B6591997-11-0404 November 1997
Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6631997-11-0404 November 1997
Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown
ML18102B6431997-10-29029 October 1997
Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing
ML18102B6391997-10-29029 October 1997
Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6491997-10-24024 October 1997
Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6461997-10-24024 October 1997
Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6321997-10-21021 October 1997
Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position
ML18102B6201997-10-14014 October 1997
Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
1999-09-10
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18102B6681997-10-0101 October 1997
Rev 8 to Inservice Testing Manual for Pumps & Valves Program.
ML18106A8291997-09-0404 September 1997
Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl
ML18102A7941997-01-21021 January 1997
Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem
ML18102A7931997-01-21021 January 1997
Event Classification Guide,Technical Basis, Salem Generating Station
ML18102A6661996-11-19019 November 1996
Rev 2 to Pse&G Simulation Facility Certification Program.
ML20115B7791996-07-0303 July 1996
Final Draft, Hope Creek Event Classification Guide, Sections 1-9
ML18101B1141995-11-14014 November 1995
Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML18101A7711995-05-11011 May 1995
Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan.
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML18101A6751995-02-16016 February 1995
Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
ML18101A6761995-02-16016 February 1995
Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response.
ML18101A5381995-01-27027 January 1995
Revised Salem Generating Station Event Classification Guide.
ML18101A2111994-08-17017 August 1994
Revised Salem Event Classification Guide.
ML18101A6771994-07-11011 July 1994
Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination.
ML20147B1601994-04-23023 April 1994
Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A8081994-01-0707 January 1994
Rev 30 to Salem Generating Station Event Classification Guide.
ML20147B1491993-11-0202 November 1993
Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A4201993-06-15015 June 1993
Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures.
ML18100A3771993-05-0505 May 1993
Rev 27 to Salem Generating Station Event Classification Guide.
ML18100A3661993-04-27027 April 1993
Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6
ML20147B1171993-04-13013 April 1993
Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML18096B2911993-02-10010 February 1993
Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18
ML20147B1021993-01-21021 January 1993
Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process
ML20135B6521992-12-29029 December 1992
Rev 0 to Loss of Overhead Annunciator Sys
ML20147B1371992-12-22022 December 1992
Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML18096A9601992-08-28028 August 1992
Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan.
ML18100A3151992-07-28028 July 1992
Rev 1 to Process Computer Maint & Mod Control Program.
ML18096B3191992-07-17017 July 1992
Rev 8 to Salem Nuclear Generating Station Odcm.
ML20147B1691992-05-0707 May 1992
Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications
ML18096A6791992-04-30030 April 1992
Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan.
ML18096A4421992-01-15015 January 1992
Rev 17 to Salem Generating Station Event Classification Guide
ML18096A3211991-10-0404 October 1991
Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18096A1431991-06-28028 June 1991
Rev 12 to Salem Generating Station Event Classification Guide.
ML18095A9661991-05-30030 May 1991
Artificial Island Salem Event Classification Guide, Rev 11
ML18096A1191991-05-28028 May 1991
Rev 2 to NFU-0039, Salem Reactor Physics Methods.
ML18095A9391991-05-16016 May 1991
Revised Replacement Pages to Facility Inservice Testing Program
1999-09-10
[Table view] |
Text
e* Page I of 3 SALEM OPERATIONS l-EOP-TRIP-3, Rev. 10 SAFETY INJECTION TERMINATION USE CATEGORY:
I REVISION
SUMMARY
- This is a major revision to the EOP's. Revision Bars are not utilized for this change. The revision numbers for all EOPs will move to rev. I 0. Presently, each EOP flowchart has its own respective revision number associated with it such that for a given procedure, EOP-SGTR-1 for example, the revision number on each flowchart is not the same. Future revisions to the EOPs will revise all documents associated with that specific procedure.
i.e., when a change is made to EOP-TRIP-2, all EOP-TRIP-2 flowcharts and cover sheets will be updated to the same revision number. The conditional action step before resetting Safety Injection (SI) has changed to address any single vital bus blackout.
This change is a result of a revision request which addresses the required operator action should a single bus blackout loading occur. The intent of this step is that if a single bus blackout occurs after the SI is reset then the operator should reset the Safeguards Equipment Cabinet (SEC) and start Safeguards loads in accordance with the supplied table. IMPLEMENTATION REQUIREMENTS:
OPERATI:m SALEM APPROVE°t DATE.* 7-11-2t I PDR ADOCK 05000272 S PDR Page 2 of 3 SALEM OPERATIONS 1-EOP-TRIP-3, Rev. 10 SAFETY INJECTION TERMINATION USE CATEGORY:
I REVISION
SUMMARY
CONTINUATION:
Deleted section warning operators that Reactor Coolant System (RCS) temperature indications and interlocks may be inaccurate when on Natural Circulation.
This caution, as referenced in the Emergency Response Guide (ERG) background document, applies to plants with Resistance Temperature Detector (RTD) bypass manifolds which require Reactor Coolant Pumps (RCP) in service to provide flow through the manifold.
Salem uses imbedded R TD elements in the loops which indicate loop temperature independent of RCP operation.
As an enhancement RCP Seal Cooling now requires both Seal Injection and Thermal Barrier cooling be established to RCPs. Various procedures have added the precaution to not start an RCP, if seal cooling had been previously lost, until an RCP evaluation has been completed.
This precaution is now standard in all EOPs where applicable.
The basis for this step is to evaluate for possible introduction of crud into the seal package from RCS back leakage. Pressurizer (PZR) level adverse setpoints have changed as a result of ERG footnotes and new methods of calculating uncertainties and adverse allowances.
PZR level setpoints have changed form 26% to 35% and from 11% to 21%. See SC-RC002-0l for detailed analysis.
Restoration of Service Water to the Turbine Building has been standardized.
Continuous Action Summary (CAS) for EOPs have been standardized in most cases. The verbiage and the content of the CAS action steps are more consistently worded. Additionally the size, shape and location of the CAS's are now standardized.
.. Page 3 of 3 SALEM OPERA TIO NS l-EOP-TRIP-3, Rev. 10 SAFETY INJECTION TERMINATION USE CATEGORY:
I REVISION
SUMMARY
CONTINUATION:
Cartesian markers are no longer used on the flowcharts.
Coordinate markers i.e., sh-2 H, 17 are no more. Procedure references have been changed to incorporate the Procedure Maintenance Group (PMG) nomenclature and numbering system.
EMERGENCY OPERATING PROCEDURE EOP-TRIP-3 SAFETY INJECTION TERMINATION
1.0 Entry
Conditions See Flowchart
2.0 Operator
Actions 2.1 Immediate Actions None 2.2 Subsequent Actions See Flowchart
3.0 Attachments
List 3.1 Tables Table 1, Post Safety Injection Data CAS TABLE 1-1 3.2 Figures None 3.3 Graphs None 3.4 Check Off Sheets None End of Procedure Final Page Salem Unit 1 1 Rev. 10 PAGE CHANGE CONTROL SHEET List of pages 1-EOP-TRIP-3 SHEET 1 Rev. 10 l-EOP-TRIP-3 SHEET 2 Rev. 10 1-EOP-TRIP-3 SHEET 3 Rev. 10 1-EOP-TRIP-3 TAB 1-1 Rev. 10 1-EOP-TRIP-3 CAS TABLE 1-1 Rev. 10 Salem Unit 1 2 Rev. 10 TABLE 1 POST SAFETY INJECTION DATA Initial Pressurizer Level Final Pressurizer Level Initial Pressurizer Pressure Final Pressurizer Pressure Initial Tavg Final Tavg RWST Temperature (T0650A) Duration of Safety Injection Initial RWST Level Final RWST Level Date Reviewed by (Senior) Nuclear Shift Supervisor Date -----Salem Unit 1 3 Rev. 10
- e. ' . TABLE 1 CONTINUOUS ACTION
SUMMARY
CONDITION RCS SUBCOOLING LESS THAN l0°F OR PZR LEVEL LESS THAN 9% (21% ADVERSE) LESS THAN TWO VITAL BUSES ENERGIZED AFST LEVEL LESS THEN 14% SALEM UNIT 1 TABLE 1-1 EOP-TRIP-3 ACTION OPERATE ECCS EQUPIMENT TO RESTORE SUBCOOLING AND PZR LEVEL GO TO EOP-LOPA-1 SHIFT AFW PUMP SUCTION REV 10 2 3 4 5 6 7 _B 9 10 11 12 13 14 15 16 .P 18 19 20 21 22 l-EOl'*TRJP-3 SAF£TY T£RHINATTON J I-COP-TRIP
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