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. 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[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
SALEM OPERATIONS l-EOP-TRIP-2, Rev. 12 REACTOR TRIP RESPONSE USE CATEGORY: I REVISION
SUMMARY
- The following changes are editorial (Revision Bars were not utilized for this change):
+ Step 3 on sheet 1 has been changed to remove the action steps which manipulated the MSlO controls.
These controls were enhanced in DCP lEC-3325 and remote board operation is no longer required to relbOve the "reset and windup" within the valve controller.
+ Step 10 on sheet 1 has been changed due to PSE-94-776, Salem RCP Seal Injection Path Resistance Calculation. Seal Injection flow rate is 6 to 10 GPM vice the old 6 to 13 GPM. This new value is to ensure that the operating nows for charging and seal injection will be met while still maintaining the limiting accident ECCS flow.
- Step 16 on sheet 2 has been changed to update this procedure to the Tech. Spec. Amendment which altered our SIG Lo-Lo Trip setpoint. The setpoint was changed to 9% and affects our AFW Interlock.
Step 16 has been revised as follows:
WHEN AT !&\§! I!IBfili. SG Lo-Lo LEVEL BISTABLES ARE RESET AS INDICATED BY:
- BEZEL INDICATION THEN SEND OPERATOR TO RESET IMS52 IMPLEMENTATION REQUIREMENTS:
- Issue of Information Directive 95-004 9505020324 950421 \'
PDR ADOCK 05000272 I S PDR ,
EOP-TRIP-l TABLEl CONTINUOUS ACTION
SUMMARY
CONDIDON ACTION RCPs WITIIOUT CCW STOPRCPs SI ACTUATION GO TO EOP-TRIP-1 STEP 7 LESS THAN TWO VITAL BUSES ENERGIZED GO TO EOP-LOPA-1 AFST LEVEL LESS THAN 14% SHIFT AFW PUMP SUCTION SALEMUNITl TABLE 1-1 REV.12
EMERGENCY OPERATING PROCEDURE EOP-TRIP-2 REACTOR TRIP RESPONSE 1.0 Entry Conditions See Flow Chart 2.0 Operator Actions 2.1 Immediate Actions None 2.2 Subsequent Actions See Flowchart 3.0 Attachments List 3.1 Tables CAS TABLE 1-1 3.2 Figures None 3.3 Graphs None 3.4 Check Off Sheets None End of Procedure Final Page SALEMUNITl Page 1 REV 1:2
PAGE CHANGE CONTROL SHEET List of Pages 1-EOP-TRIP-2 SHEETl Rev.12 l-EOP-TRIP-2 SHEET2 Rev.12 1-EOP-TRIP-2 SHEETJ Rev.12 1-EOP-TRIP-2 SHEET4 Rev.12 1-EOP-TRIP-2 CAS TABLE 1-1 Rev. 12 SALEMUNITl Page 2 REV12
SC.OP-DD.Z7rAD44(Q)
A'ITACHMENT 1 EOP CHANGE REQUEST DISPOSITION FORM Procedure Number: 1-EOP-TRIP-2 Date Received: 8 Feb.1995
~--------~----------------
Procedure
Title:
REACTOR TRIP RESPONSE EOP Change Request Number Assigned: 95-003 Disposition: 1. The change request:
181 a) warrants a change D b) does not warrant a change (see comments)
D c) requires :further research (see comments)
- 2. If a change is warranted, it will be made:
181 a) immediately (within two weeks)
Db) when the next full revision is made to the procedure (see comments)
D c) prior to full revision (see comments)
- 3. Training requirements:
[8] a) Information Directive D b) Shift Briefing D c) Simulator Session Comments: First, l-EOP-TRIP-2 is being revised to remove the steps which manipulate the MSlO controls. These controls were enhanced in DCP IEC-332S and remote board operation is no longer required to remove the "reset and windup" within the valve controller. Second, Seal Water Injection flow rate has been changed to 6 to 10 GPM. This change came about due to PSE-94-776, Salem RCP Seal Injection Path Resistance Calculation. Finally, Tech. Specs. have been amended changing the S/G Lo-Lo Trip setpoint which affects the AFW Interlock , SIG sample valves, and the reset on the MS52.
Prepared: Jeff Beattie ~ Date: 9 Feb. 1995
~--~--~(E_O_W~~-OP~Coo-----r-.~M--!or-)-----+-.(}'Lf-=--------------
Verified: ~e.,..Zt2.
~---f<----::i~7(~0per:::::::atin~*~gE~o~gin=e=~*)~~-----------====;:::>-~
Date:
Salem Common Page 65 of91 Rev.1
SC.OP-DD.ZZ-AD44(Q)
ATTACHMENT 2 EMERGENCY OPERATING PROCEDURE APPROVAL COVER PAGE Procedure Number:
Procedure
Title:
REACTOR TRIP RESPONSE Unit Number: 1 Revision Number: 12 Remarks:
- The following changes are editorial (Revision Bars were not utilized for this change):
- Step 3 on sheet 1 has been changed to remove the action steps which manipulated the MS10 controls.
These controls were enhanced in DCP tEC-3325 and remote board operation is no longer required to remove the "reset and windup" within the valve controller.
- Step 10 on sheet 1 bas been changed due to PSE-94-776, Salem RCP Seal Injection Path Resistance Calculation. Seal Injection flow rate is 6 to 10 GPM vice the old 6 to 13 GPM. This new value is to ensure that the operating flows for charging and seal injection wiU be met while still maintaining the limiting accident ECCS flow.
- Step 16 on sheet 2 has been changed to update this procedure to the Tech. Spec. Amendment which altered our SIG Lo-Lo Trip setpoint. The setpoint was changed to 9% and affects our AFW Interlock.
Step 16 bas been revised all follows:
WHEN AT LEAST THREE SG Lo-Lo LEVEL BISTABLES ARE RESET AS INDICATED BY:
- BEZELINDICATION THEN SEND OPERATOR TO RESET lMSSl
REVIEW I APPROVAL------------
SOTS: Date:
Senior Reactor Operator:
! \ .1 Operating Engineer: _ _ _......_v.:_.-..;.;1--'---.:..=**-=----'Ls'/')--;) /.
-L-:::,,,.,___,_*;-_*___..;..-:.;_*_-_.~......1_ _ _ _ Date:
(
Salem Common Page 66 of91. Rev.1
ATTACHMENT 3
EDITORIAL VERIFICATION FORM Evaluator (SRO): ---~-.(-~_.\.,..)11.....~t:_J__________ Date: l l t ') )~ ')
Procedure Number: 12 Procedure
Title:
REACTOR TRIP RESPONSE VERIFICATION CRITERIA DISCREPANCY NUMBER Jt;'
- 1. Legibility
- 2. Format Consistency
,,, It.
fl.
- 3. Identification Information
- 4. Information Presentation
- 5. Procedure Referencing NOTE For each discrepancy, a Verification Discrepancy Sheet (Attachment 4) is required to be rdled out and attached to this form.
Evaluation Complete:
l....__, /" ( Evaluator Sign I Date )
Discrepancies Resolved and Incorporated:
OP Coordinator Sign I Date )
Editorial Verification Form I Resolutions Reviewed:
._ cf);_
Salem Common Page 67 of91 Rev. I
SC.OP-DD.ZZ-AD44(Q)
ATIACHMENT 5 TECHNICAL VERIFICATION FORM Procedure Number: 1-EOP-TRJP-2 Draft Revision: 12 Procedure
Title:
REACTOR TRIP RESPONSE Evaluator(s): ~ . [\**-1:;1J Scope of Verification: Full Partial ( specify steps or sections )
TABLE TOP V&V. Verify the bullets listed under the REVISION
SUMMARY
. Follow the guidance provided in SC.OP-DD.ZZ-AD44(Z) Sections 7.0 & 10.5.
VERIFICATION CRITERIA DISCREPANCY NUMBER Jr* i .1 111
- 1) Source Documents
- 2) Quantitative Values i' itr
- 3) Plant Hardware I
- 4) Conformance Items :'f flJ(
NOTE For each discrepancy, a Verification Discrepancy Sheet (Attachment 4) is required to be filled out and attached to this form.
C) *. * (
Evaluation Complete: c '\\ '"\1
=._/ (Evaluator Sign I Date)
Discrepancies Resolved and Incorporated:
(EOP/
Technical Verification F onn I Final
/'l**) (
l) :I Resolutions Reviewed: ~;:;:....~?>--**. .. *!.-,
( Operating Engineer Sign I Date ) (J Salem Common Page69 of91 Rev.1
SC.OP-DD.ZZ-AD44(Q)
ATIACHMENT 6 TECHNICAL VALIDATION FORM Procedure Number: 1-EOP-TRIP-2 Date Performed:
Procedure
Title:
REACTOR TRIP RESPONSE Draft Revision: 12 Validation Method: TABLE TOP
~~~-- -------------------------------
Validation Scope: Verify the bullets listed under the REVISION
SUMMARY
. Follow the guidance provided in SC.OP-DD.ZZ-AD44(Z) Sections 7.0 & 10.5.
Plant Operations Personnel: Qualifications (SRO, RO etc.)
~ (". '\
\t ,,_; '1*\fV
'I - "* ~
sru Validation team Members Organization and Title JeffBeattie ~~ Ops-EOP I AOP Coordinator Ops-SRO A-NOTE For each Discrepancy, a Verification Discrepancy Sheet (Attachment 7) is required to be filled out and attached to this form.
Validation Exercise Completed:
(EOP/AO Discrepancies Resolved and Incorporated:
Validations and Resolutions Reviewed and Approved:
/ I ~
Salem Common Page70 of91 Rcv.1
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