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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999
Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10
ML20216E6201999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9
ML20211F9511999-08-26026 August 1999
Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool
ML20196E6541999-06-21021 June 1999
Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively
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
ML20195B5531999-05-24024 May 1999
Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature
ML20196L1231999-05-17017 May 1999
Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys
ML20206T8941999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9
ML20206G2111999-04-30030 April 1999
Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements
ML20206G2281999-03-31031 March 1999
Rev 18 to ODCM for Hope Creek Generating Station
ML20205E8101999-03-29029 March 1999
Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements
ML20204J2871999-03-22022 March 1999
Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors
ML20204J1291999-03-22022 March 1999
Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101
ML20202B6171999-01-19019 January 1999
Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML20198T0281998-12-30030 December 1998
Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements
ML20198N3981998-12-28028 December 1998
Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys
ML20198C9641998-12-16016 December 1998
Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures
ML20155D3591998-10-22022 October 1998
Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits
ML20154R5871998-10-19019 October 1998
Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities
ML20154L5021998-10-0808 October 1998
Revised Tech Spec Page,Which Corrects Editorial Errors
ML20151X7321998-09-0808 September 1998
Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries
ML20151S4331998-08-25025 August 1998
Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs
ML20236F1171998-06-25025 June 1998
Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities
ML20249A8181998-06-12012 June 1998
Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design
ML20247K7381998-05-13013 May 1998
Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements
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
ML20217P9351998-04-28028 April 1998
Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances
ML20216F4541998-03-0606 March 1998
Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML20197H5941997-12-19019 December 1997
Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program
ML20197H8511997-12-0808 December 1997
Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006
ML20198J6431997-10-10010 October 1997
Rev 0 to 55-WP3/F43TB3-05, Weld Procedure
ML20211M6121997-10-0707 October 1997
Cycle 4 Startup Physics Testing
ML20211M2401997-10-0303 October 1997
Proposed Tech Specs Pages Associated W/Slmcpr Changes
ML20217D3761997-09-29029 September 1997
Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated
ML20211F6201997-09-24024 September 1997
Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves
ML20198H2471997-08-26026 August 1997
Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs
ML20217Q6731997-08-26026 August 1997
Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements
ML20211M2641997-08-26026 August 1997
Revised TS Bases Pages for Amend 101 to License NPF-57
ML20217Q3081997-08-25025 August 1997
Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits
ML20198J6541997-08-20020 August 1997
Rev 3 to 55-PQ7001-03, Procedure Qualification Record
ML20198J6501997-08-20020 August 1997
Rev 5 to WP3/F43TB3-05, Welding Procedure Specification
ML20210P3471997-08-20020 August 1997
Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage
ML20149G4301997-07-16016 July 1997
Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio
ML20211M2531997-07-16016 July 1997
Sanitized Version of TS Page Changes Re SLMCPR
ML20141C1621997-06-19019 June 1997
Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10%
ML20140D2201997-05-30030 May 1997
Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments
ML20141G8291997-05-19019 May 1997
Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program
ML20137N6271997-04-0101 April 1997
Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity
ML20137M1331997-03-31031 March 1997
Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20216E6201999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9
ML20206T8941999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9
ML20206G2281999-03-31031 March 1999
Rev 18 to ODCM for Hope Creek Generating Station
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
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML20197H8511997-12-0808 December 1997
Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006
ML20198J6431997-10-10010 October 1997
Rev 0 to 55-WP3/F43TB3-05, Weld Procedure
ML20198J6501997-08-20020 August 1997
Rev 5 to WP3/F43TB3-05, Welding Procedure Specification
ML20198J6541997-08-20020 August 1997
Rev 3 to 55-PQ7001-03, Procedure Qualification Record
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
ML20096F4741996-01-13013 January 1996
Revised Hope Creek Generating Station Event Classification Guide, Including Rev 45 to Table of Contents,Rev 39 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 26 to Attachment 7 & Rev 26 to Attachment 9
ML20096C2231995-12-19019 December 1995
Rev 0 to HC.SA-AP.ZZ-0005(Z), Operational Readiness Self Assessment Program
ML20096C2151995-11-26026 November 1995
Rev 0 to Hope Creek RF06 Outage Completion Plan
ML20094P1151995-11-14014 November 1995
Revised Hope Creek Event Classification Guide, Including Rev 44 to Table of Contents,Rev 38 to Attachments Signature Page & Rev 25 to Attachments 6,7 & 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML20086G1341995-07-21021 July 1995
Rev 42 to Hope Creek Generating Station Event Classification Guide
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML20076F9021994-10-14014 October 1994
Event Classification Guide
ML20073D3671994-09-20020 September 1994
Rev 3 to IST Program,Including Review Sheets to Add 17 Valves,Three Revised Pump Review Sheets,Reflecting Testing Requirements of Relief Request P3 & Review Sheets for Two Valves Which Had Testing Requirements Changed
ML20071J9801994-07-15015 July 1994
Revised Hope Creek Event Classification Guide
ML20069N2071994-06-0909 June 1994
Revised Hope Creek Generating Station Event Classification Guide,Including Rev 33 to Table of Contents,Rev 12 to Attachment 1,Page 5 & Rev 7 to Attachment 2,Page 4
ML20069D2961994-05-21021 May 1994
Revised Event Classification Guide,Including Rev 33 to Table of Contents,Rev 28 to Attachments Signature Page,Rev 12 to Attachment 1,Rev 7 to Attachment 2,Rev 7 to Attachment 3,Rev 6 to Attachment 4 & Rev 18 to Attachment 6
ML20147B0941993-12-13013 December 1993
Rev 10 to Procedure HC.IC-GP.ZZ-0008(Q), Maint Troubleshooting & Known Component Problems
ML20046D3311993-08-0909 August 1993
Rev 3 to Section 7,Page 3 of Hope Creek Event Classification Guide, Rev 28
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML20147B0681992-11-17017 November 1992
Rev 4 to Procedure NC.NA-AP.ZZ-0005(Q), Station Operating Procedures
ML20106B8541992-09-25025 September 1992
Revised Event Classification Guide (Ecg),Including Rev 21 to Table of Contents,Rev 13 to Ecg Section Signature Pages 1 & 2 & Rev 3 to Ecg Section 6 Re Fission Product Boundary Failures
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML20079K5391991-10-0404 October 1991
Rev 14 to Event Classification Guide,Including Table of Contents,Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18100A7071991-02-0707 February 1991
Rev 1 to Procedure NC.NA-AP.ZZ-0061(Q), Significant Event Response Team Mgt. Procedure Reformatted to Comply W/ Artificial Island Administrative Writers Guide NC.NA-WG.ZZ-0001(Z)
ML20067D7901991-01-11011 January 1991
Re 10 to Hope Creek Generating Station Event Classification Guide
ML20059D2641990-03-30030 March 1990
Rev 11 to ODCM for Hope Creek Generating Station
ML20005D6431989-11-29029 November 1989
Forwards Rev 3 to Ecg Signature Page,Rev 2 to Section 5, Fuel Damage/Degraded Core & Rev 1 to Section 6, Fission Product Boundary Failures.
ML20236B0061988-10-31031 October 1988
Rev 2 to Process Control Program Manual
ML20153F3361988-06-0808 June 1988
Rev 9 to Offsite Dose Calculation Manual
ML20151P5851987-12-0202 December 1987
SPDS Verification & Validation Program Plan
ML20236Q8671987-09-30030 September 1987
Amend 1 to Rev 1 to Inservice Testing Program (Pumps & Valves)
ML20235E1541987-09-15015 September 1987
Rev 1 to Hope Creek Generating Station Inservice Testing Program (Pumps & Valves)
ML20238E7621987-09-0909 September 1987
Emergency Plan Annual Exercise
ML20237K0671987-08-0505 August 1987
Rev 8 to Offsite Dose Calculation Manual
ML18092B4991987-03-20020 March 1987
Artificial Island Stability Limitation Operating Restrictions.
ML20212B7171987-02-25025 February 1987
Rev 6 to Offsite Dose Calculation Manual for Hope Creek Generating Station
ML20214N7251986-11-30030 November 1986
Process Control Program
ML20203N8491986-09-30030 September 1986
Inservice Exam Program Submittal for First 10-Yr Interval
ML20203K7691986-08-13013 August 1986
Rev 0 to Spec AEI-PSEG-SP-002, Spec for Bailey 862 Solid- State Logic Module Reliability Test Program for Pse&G Hope Creek Generating Station
ML20214Q8161986-03-14014 March 1986
Rev 1 to OP-AB.ZZ-121(Q), Failed Open Safety/Relief Valve
1999-09-10
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Text
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PSEGG NUCLEAR DEPARTMENT Page 1 of 1
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NC.NA-AP.25-0005(Q) REY. 4 gg STATION OPERATING PRACTICE 8 044 i SPONSOR ORGANIEATION: Hope Creek Operations j _
1 REVISION
SUMMARY
- This is a Minor Revision that containts only
.' typographical and editorial changes. .
This change clarifies that the Test Manager must be a Station Line
] Management individual. The change also deletes two examples from j the definition of special test.
i i
! IMPLEMENTATION REOUIREMENTS
}
j , 1. Implementation is effective immediately 1
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1 APPROVED: h_ _
// 7 Ge er E sg r - Hope Creek Operations /Dpe CONCUR: M[4 ) ~-
General Manager - Quality Assurance / Date Nuclear Safety Review APPROVED:
General Manager - Salem Operations Date 9701290353 970124 PDR FOIA O'NEILL96-351 PDR
NC.NA-AP.22-0005(Q)
CD-190A 5.7 Procedure Requirements CD-484Y CD-89sE 5.7.1 Detailed written pt.ocedures are required in the Muclear CD-17$0 Department for actions and activities that affect the CD-152F health and safety of the public except simple, CD-898E CD-147Y rrt. tine activities that can'be performed by qualified personnel with normal skills. Specific requirements and criteria are identifled in NC.NA-AP.ZZ-0001(Q), Nuclear Department Procedure System and NC.NA-AP.ZZ-0032 (Q) ,
Preparation, Review an d Approval of Procedures.
The designation of these activities requiring detailed precedures la mada by the cognizant department heads and as a mininve, complies with applicable requirements of Reg Guide 1.33 Rev. 2 and the Unit's Technical Specifications. Examples of activities that may not require a written procedure are:
CD-147Y -
Routine shift operating activities such as '
adjusting or manipulating selector switches, electrical control devicec, and damping or throttling devices whe:1 required for normal plant operation such as whe,r reading instrumentation or maintaining a precaribed operating parameter or condition.
CD-147Y -
Maintenance activities conducted via approved work l request / work orders which replace, remove, or install electrical or mechanical devices where there is no disassembly of active parts or components and the activity only requires ;
disconnecting wiring (does not involve soldering or i termination kits and removing tasteners or other !
mounting devices)(no special torque requirements j are inv'alved) and there are no special '
preinstallation or preremoval inspection test requirements. The affected component shall be left in the approved design contiguration. Examples of l components in this category are:
Fuses
+
Fuseholders Switches Circuit Breakers and Motor Control Center Starters 1 4
+ Light Bulbs j 4
- Relays Instrument Transmitters or Sensors (does not involve welding or brazing)
Meters and gauges (does not involve welding or brazing)
Fasteners Solid State Trips Units Circuit Boards a
Transducers Nuclear CO non Page 16 of 54 Rev. 4
_ ___ . - _ _ . _ _ . _ _ . _ .~
NC.NA-AP.EE-0005(Q)
Shunts Valve handwheels Valve packing Strainers and Filters CD-147Y 5.7.2 Where written procedures are not used, applicable controlled design documents shall be referenced on the work order (for example, drawings, specifications, vendor manuals, etc. that are controlled IAW NC.NA-AP.ZZ-0003(Q), Document Control Program).
Sufficient reference shall be made to ensure compliance with design requirements (for example, material requirements, mounting details, electrical wiring requirements . Attachment 2 provides additional direction reg)arding procedures and work instruction if procedures are not required for a specific job.
CD-147Y 5.7.3 Procedures and procedure revisions shall be prepared reviewed and approved in accordance with NC.NA-AP.ZZ-0032(Q).
CD-195A 5.7.4' There shall be no deviation from written procedures
-CD-179C except as described in step 5.7.5 below. Procedures CD-898E shall be followed exactl,y as written and in the order '
CD-152F specified. Step 5.7.5 provides mandatory rules for CD-200A " deviating from procedures". Use of these rules to e 147Y deviate from Q, F, or R procedures mandates a one hour 459A- report be submitted to the NRC for invoking CD-145Y 10CFR50.54(x). Any authorirad deviation from the procedure sequence shall be specified in the procedure, where applicable. If the procedure can not be performed as written, the activity should be stopped and :
supervisory personnel consulted. On the spot changes to written procedures shall be performed in accordance with NC.NA-AP.ZZ-0032(Q).
CD-145Y 5.7.5 Deviating from procedures '
CD-147Y
.a. Deviating from procedure requirements is permitted in an emergency situation only under All of the following circumstances:
Such action'is immediately necessary to '
protect th's health and safety of the public or plant personnel, or to prevent damage to plant equipment that could adversely affect public or plant personnel health and safety; And
+
No equivalent action consistent with procedural requirements is immediately apparent; And Nuclear Common Page 17 of 54 Rev. 4
NC.NA-AP.EE-0005(Q)
The action is reasonable based on the information available at the time and the deviation is the minimum required to meet the emergency; and Insufficient time exists to modify the procedure IAW the requirements of NC.NA-AP.ZZ-0001(Q) and NC.NA-AP.ZZ-0032(Q);
And l
- The action is taken only for the duration of l the emergency situation,
- b. Any such deviation shall not be made unless approved by a licensed Senior Reactor Operator who is a member of the operating shift of the affected unit. The deviation shall be documented and reported to the NRC prior to action l
.being taken if possible, but in all cases IAW the Emergency Classification Guide (ECG), Section 18
, and NC.NA-AP.ZZ-0006(Q), Incident Report / Reportable l
Event Program and Quality / Safety Concerns Reporting System CD-379X 5.8 Key Control CD-637X 5.8.1 Departments responsible for controlling keys to vital areas shall have a department procedure or directive to ensure the accountability of keys and their discriminate use.
5.8.2 Keys for the operation of certain switches, valves, and swltchgear, and keys for rooms, electrical cabinets, computer enclosures, etc. (except for keys to High Radiation Department.
Areas) shall be controlled by the operations 5.8.3 Keys for those areas where instrument setpoint devices
( are located shall be controlled by the Maintenance l . Department. These keys shall not be used without the I
' knowledge and consent of the Control Room Nuclear Control Operator. Notification of the start or conclusion of an approved procedure that employs these l- keys is sufficient.
5.8.4 Keys to High Radiation Areas shall be controlled by the Radiation Protection Department.
, 5.8.5 Keys for entry into Vital and Protected Area boundaries Flaall be Controlled by the Security Department.
5.8.6 Keys for the Fire Protection System shall be controlled
\
by the Nuclear Site Protection Department.
1 Nuclear Common Page 18 of 54 Rev. 4
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