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
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{{#Wiki_filter:SALEM GENERATING STATION INSTRUCTOR LESSON PLAN TITLE: ATWT LESSON NO.:
DURATION:
REVISION NO.: 0 DATE: 3-08-83 SUBMITTED: Rick~ DATE: 3-08-83 APPROVED-: <f% -£. DATE: b'P'ff'?
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INSTRUCTOR
REFERENCES:
TRAINING MATERIAL REQUIRED:
STUDENT HANDOUTS:
CLASSROOM REQUIREMENTS: I i
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Title:
ATWT NOTES III. Solid State Protection System Review A. Basic design function is to protect the core and ultimately to prevent fission product releases to the environment.
- 1. To ensure reliability in the design:
0 Redundancy 0 Independance 0 Diversity 0 Fail safe 0 Testability B. Re~undancy/Independance Redundancy ensures that a single failure of
- an instrument channel will not prevent proper protective action when required. To enhance redundancy a coincidence circuitry is used.
Two independant and redundant protection trains (A and B) both receiving identical info and both being able to trip the reactor arid actuate ESF. The instrument channels feeding the protection trains are both phy~ically and electrically separated.
AC operated relays at the input of the trains provide electrical isolation between the inputs and the train logic. SSPS outputs are thru contacts which are operated by slave relays again providing electrical separation.
C. Multiplexing The function of the multiplexing is to efficiently pass large amts. of info over the least number of conductors as possible. To do this a time-sharing technique is used.
There are on the order of 2..00 lamps, 100 annunciators and 200 signals fed to the computer.
SAOP8303:3 Page 1 'Date 03/08/83 Rev. 0
Title:
ATWT NOTES D. Protection Scheme/Signal Path TP-1 Example all 4 B/S supply both Trains. They operate their own Relays which operate contacts at the Input Bay. When the correct logic is made up the output relay operates which operates its contact to perform the safegaurd actuation/rx trip. The noR" cable between the trains allows either train to operate the Rx Status or Computer demultiplexer.
For a Rx trip note that 'A' train deenergizes the 48V UV relay for the 'A' breaker and the
'B' bypass and the 'B' train gets the 'B' bkr and 'A' bypass.
SAOP8303:3 Page 2 Date 03/08/83' Rev. 0
SALEM GENERATING STATION INSTRUCTOR LESSON PLAN TITLE: ATWT LESSON NO.:
DURATION:
REVISION NO.: 0 DATE: 3-08-.83 SUBMITTED: Rick Sweeney DATE: 3-08-83 APPROVED: DATE:
I
TITLE: . ATWT NOTES Specific Indications A. Terminology
- Demand = > some SPECIFIC ACTUATION is being demanded to be performed
- Confirmation = >is confirming some given actuation has been performed B. The yellow lites on the RP-4 status panel are energized via a 28V source via a contact.
This contact is operated by a relay located in the control board demultiplexer cabinet.
The relay is being operated by the logic signal coming from the SSPS logic trains.
Thus, these yellow lites would be classified as a demand signal.
- c. Th~_red reactor trip lite on RP-4 is a TP-1 different story. The red lite is also powered from a 28V source when RTXB or RTXA contact 11/12 are closed. To actuate these relays Bkr 'B' and Bypass 'B' must be open or TP-2 Bkr 'A' and Bypass 'A' must be open.
D. Overhead Annunciators
- F-46 Reactor trip Turbine Trip Confirmation alarm - actuated when the
'A' bkr & 'A' bypass are open or 'B' bkr
& 'B' bypass are open. Note this is a confirmation alarm for the reactor and a demand for the turbine.
- F-30 Turbine Trip P7 Reactor Trip Confirmation alarm for turbine as sensed by auto-stop oil presure and TV's and demand signal for reactor.
8305-SAOP:l
TITLE: ATWT NOTES E. In accordance with the EI for reactor trip the operator is required to perform certain actions until a reactor trip is "CONFIRMED".
Confirmed by:
- RP-4 reactor trip lite
- F-46 Reac Trip Turbine Trip
- IRPI
- Rod bottom lites
- Green P.B. for rod drive bkrs
- Page 2 Date 3-8-83 8305-SAOP:l Rev.
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- SALEM GENERATING STATION I~STRUCTOR LESSON PLAN TITLE: ATWT LESSON NO.:
DURATION:
REVISION NO.: 0 DATE: 3-08-83 SUBMITTED:~~ DATE: 3-08-83 APPROVED} / DATE: i~,13
TITLE: ATWT NOTES AD-16 Post Reactor Trip/Safety Injection Review and Unit Start-Up Approval Requirements I. Responsibilities In event of SI/Rx trip the Senior Shift Supervisor:
o Perform a Post trip review The review items are listed on Form AD-16-A o E~aluate the review to ensure all equipment and systems operated as designed o Form AD-16~A cover items such as conditions prior to event testing/maintenance/evolutions in progress any major equip/systems out of service description of event sequence of events agree w/f irst out any unexpected alarms In event of SI/or Rx trip the Operations Manager:
o Review Post Trip Review 0 Ensure cause of event has been identified *
. 0 Equip operation as designed o Determine if corrective actions required prior to S/U
- Page --Date 3-8-83 8305-SAOP:l Rev. 0
TITLE: ATWT NOTES II. Approval Requirements prior to S/U.
o After planned unit outages => Operations Manager o After Reactor Trips/SI Upon satisfactory completion of hte Post trip review the Operations Manager may ~uthorize start-up.
If cause of event not clear then the results shall be reviewed by SORC.
Upon sat. completion of review then the General Manager may authorize S/U *
3-8-83 0
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