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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999
Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing
ML20209A7351999-06-23023 June 1999
Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b
ML20196B4741999-06-17017 June 1999
Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610
ML20195E9101999-06-0808 June 1999
Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested
ML20207A0761999-05-14014 May 1999
Rev 3 to CNS Strategy for Achieving Engineering Excellence
ML20206J2661999-04-22022 April 1999
CNS Offsite Dose Assessment Manual (Odam)
ML20205H2891999-03-31031 March 1999
Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions
ML20151Q0621998-07-28028 July 1998
Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS
ML20236W1141998-07-28028 July 1998
Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution
ML20236R9821998-07-16016 July 1998
Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution
ML20236Q0641998-07-13013 July 1998
Proposed Tech Specs Re Rev B to Conversion to Improved STS
ML20206P9051998-07-0707 July 1998
Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station
ML20216H0571998-04-15015 April 1998
Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements
ML20216H0801998-04-15015 April 1998
Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting
ML20216D8971998-04-0808 April 1998
Rev 1 to Strategy for Achieving Engineering Excellence
ML20216B4481998-04-0202 April 1998
Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements
ML20203G4271998-02-24024 February 1998
Rev 0 to First Ten-Year Interval Containment Insp Program for Cns
ML20202H5311998-02-11011 February 1998
Strategy for Achieving Engineering Excellence
ML20216G1571997-09-0505 September 1997
Rev 2.1 to Third 10-Yr Interval Inservice Insp Program
ML20210H5641997-08-0707 August 1997
Rev 2 to NPPD CNS Third Interval Inservice Testing Program
ML20148G3481997-05-30030 May 1997
Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle
ML20148G8531997-05-0909 May 1997
Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept
ML20138J0751997-05-0505 May 1997
Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases
ML20148B0041997-05-0202 May 1997
Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program
ML20138H3861997-04-29029 April 1997
Rev 1.2 to CNS Third Interval IST Program
ML20134K3771997-02-10010 February 1997
Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions..
ML20134E1091996-10-25025 October 1996
NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1
ML20117K3291996-06-0606 June 1996
Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation
ML20100R4431996-03-0505 March 1996
Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements
ML20101L8381995-12-31031 December 1995
Reactor Containment Bldg Integrated Leak Rate Test. W/
ML20113B0531995-12-29029 December 1995
Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components
ML20093L1901995-10-18018 October 1995
Rev 0 to Third Ten-Yr Interval ISI Program for Cns
ML20086K4421995-07-14014 July 1995
Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs
ML20086H7341995-07-14014 July 1995
Rev 7 to CNS Second Ten Yr Interval IST Program
ML20086H7601995-06-30030 June 1995
Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components
ML20086B7061995-06-28028 June 1995
Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing
ML20085J2631995-06-15015 June 1995
Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS
ML20083A7241995-05-0505 May 1995
Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46
ML20083A1341995-05-0202 May 1995
Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement
ML20083M0401995-01-20020 January 1995
Rev 1 to Restart Readiness Program
ML20083M0901995-01-13013 January 1995
Rev 2 to Startup & Power Ascension Plan
ML20149H8821994-12-27027 December 1994
Proposed Tech Specs Re Control Room Emergency Filter Sys
ML20078S5711994-12-22022 December 1994
Proposed Tech Specs Re Definition of Lco,Per GL 87-09
ML20083M0141994-11-0909 November 1994
Rev 3 to Phase 1 Plan,
ML20083M0321994-11-0808 November 1994
Rev 0 to Restart Readiness Program
ML20073J2371994-09-26026 September 1994
Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig
ML20149F9921994-09-15015 September 1994
Rev 1 to CNS Startup Plan
ML20071K9311994-07-27027 July 1994
Diagnostic Self Assessment (DSA) Implementation Plan
ML20071K1541994-07-26026 July 1994
Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System
ML20070M6671994-04-26026 April 1994
Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers
1999-06-08
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20207A0761999-05-14014 May 1999
Rev 3 to CNS Strategy for Achieving Engineering Excellence
ML20206J2661999-04-22022 April 1999
CNS Offsite Dose Assessment Manual (Odam)
ML20206P9051998-07-0707 July 1998
Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station
ML20216D8971998-04-0808 April 1998
Rev 1 to Strategy for Achieving Engineering Excellence
ML20203G4271998-02-24024 February 1998
Rev 0 to First Ten-Year Interval Containment Insp Program for Cns
ML20202H5311998-02-11011 February 1998
Strategy for Achieving Engineering Excellence
ML20216G1571997-09-0505 September 1997
Rev 2.1 to Third 10-Yr Interval Inservice Insp Program
ML20210H5641997-08-0707 August 1997
Rev 2 to NPPD CNS Third Interval Inservice Testing Program
ML20148G8531997-05-0909 May 1997
Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept
ML20138H3861997-04-29029 April 1997
Rev 1.2 to CNS Third Interval IST Program
ML20134E1091996-10-25025 October 1996
NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1
ML20113B0531995-12-29029 December 1995
Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components
ML20093L1901995-10-18018 October 1995
Rev 0 to Third Ten-Yr Interval ISI Program for Cns
ML20086H7341995-07-14014 July 1995
Rev 7 to CNS Second Ten Yr Interval IST Program
ML20086H7601995-06-30030 June 1995
Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components
ML20083M0401995-01-20020 January 1995
Rev 1 to Restart Readiness Program
ML20083M0901995-01-13013 January 1995
Rev 2 to Startup & Power Ascension Plan
ML20083M0141994-11-0909 November 1994
Rev 3 to Phase 1 Plan,
ML20083M0321994-11-0808 November 1994
Rev 0 to Restart Readiness Program
ML20149F9921994-09-15015 September 1994
Rev 1 to CNS Startup Plan
ML20071K9311994-07-27027 July 1994
Diagnostic Self Assessment (DSA) Implementation Plan
ML20065H7481994-03-31031 March 1994
Near Term Integrated Enhancement Program, 940331
ML20063L2391994-01-31031 January 1994
Jan 1994 Addenda Cooper Nuclear Station IST Program for ASME Class 1,2 & 3 Components, Rev 6
ML20058C3331993-11-17017 November 1993
Rev 1 to Procedure MIUB-W812, Ultrasonic Insp of Pressure Retaining Bolting Two Inches or Greater in Diameter
ML20058C3501993-11-15015 November 1993
Rev 0 to Procedure GE-UT-307, Procedure for Ultrasonic Exam of Reactor Pressure Vessel Closure Studs
ML20128P0451992-12-21021 December 1992
Dec 1992 Addenda to Rev 6 to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components
ML20118A6151992-07-31031 July 1992
Jul 1992 Addenda to Rev 6 to Inservice Testing Program for ASME Class 1,2, & 3 Components
ML20091K1831991-12-17017 December 1991
Dec 1991 Addenda to Rev 3 to Cooper Nuclear Station Inservice Insp Program for ASME Class 1,2 & 3 Components
ML20086E6161991-11-0808 November 1991
Revised Pages to Cooper Nuclear Station Inservice Insp Program
ML20085G1841991-08-31031 August 1991
Aug 1991 Addenda to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components (Rev 6)
ML20082H6371991-08-0101 August 1991
Aug 1991 Addenda to Rev 3 to Cooper Nuclear Station, Inservice Insp Program for ASME Class 1,2 & 3 Components
ML20043C7951990-05-25025 May 1990
Rev 6 to Inservice Testing Program for ASME Class 1,2 & 3 Components.
ML19332C8181989-10-31031 October 1989
October 1989 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components.
ML20246J4271989-07-31031 July 1989
Jul 1989 Addenda to Inservice Insp Program for ASME Class 1,2 & 3 Components, Rev 3
ML20247K7591989-02-28028 February 1989
Addenda to Rev 3 to, Inservice Insp Program for ASME Class 1,2 & 3 Components
ML20151U1551988-08-12012 August 1988
Long-Term Plan for Code Qualification of Seismic Class 1S Pipe Supports Cooper Nuclear Station
ML20235U4221987-09-21021 September 1987
Reportability Analysis for 10CFR50.50 to Rev 5 to Engineering Procedure 3.3, Station Safety Evaluations. Related Info Encl
ML20235U4091987-09-21021 September 1987
Temporary Mod Sheet to Rev 2 to Conduct of Operations Procedure 2.0.7, Plant Temporary Mod Control
ML20235T2711987-08-20020 August 1987
1987 Annual Emergency Preparedness Exercise
ML20153F0491987-06-0101 June 1987
Addenda to Rev 3 to Inservice Insp Program for ASME Class 1 2 & 3 Components
ML20212D6301986-12-18018 December 1986
Fitness for Duty Policy
ML20064A6961986-12-0202 December 1986
App I to PEI-TR-870200-01 Test Procedure for Steam Accident Test of Limitorque Control & Power Wiring & Okonite Tape Splices
ML20211B4891986-09-30030 September 1986
Rev 4 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station
ML20211B4971986-09-30030 September 1986
Rev 5 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station
ML20214W0111986-08-22022 August 1986
Rev 2 to Procedures Generation Package
ML20212B9141986-07-31031 July 1986
Vols I & II of Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program
ML20211B4851986-07-31031 July 1986
Draft Rev 3 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station
ML20211B4751986-06-30030 June 1986
Rev 2 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station
ML20206T6551986-06-12012 June 1986
Rev 13 to Surveillance Procedure 6.3.2.1, Automatic Depressurization Sys Manual Valve Actuation
ML20206T6791986-06-12012 June 1986
Rev 23 to Surveillance Procedure 6.3.3.1, HPCI Test Mode Surveillance Operation
1999-05-14
[Table view] |
Text
COOPER NUCLEAR STATION SECURITY FRULEULKE5 TNTERIM PROCEDURE SP-10 SECURITY LOGS AND REPORTS INTERIM PROCEDURE I. PURPOSE A. The purpose of this Interim Procedure is to provide specific guidance for the method in which security logs and reports are maintained and controlled, and for identifying, evaluating and reporting security incidents to ensure that timely NRC notifications are made.
II. DEFINITIONS A. Unusual Occurrence.
An occurrence that is not ordinary practice or in the ordinary cause of station events.
B. Security Incident.
An incident which significantly threatens or lessens the level of station security as required by the CNS Safeguards Plan.
III. LIMITATIONS A. This procedure applies only to the logging and reporting of Unusual Occurrences and Security Incidents that take place on Nebraska Public Power District property or unusual occurrences and security incidents that are explicit or potential threats to the station, of thef t or radiological sabotage, which occur outside the owner controlled area.
IV. PROCEDURE A. 9ecurity Shift Supervisor's Log.
- 1. The Security Shift Supervisor is responsible for maintaining and controlling the Security Log which will be primarily located at CAS.
- 2. Entries will be made in permanent ink and in a chronological order.
- 3. Entries will be made to the log as soon as practical after the occurrence of incident.
- 4. The basic minimum requirements for logging shift activities are:
8508190208 050808 PDR ADOCK 05000298 F PDR n _
~
R;vis:d By/Date a p to / Rev Procedure Page 1 Of
% view 8- g .p r-- 0 SP-10 3 Pages A C/4/ k _
.4 ,
f a
- a. A heading which consists of date, hours of shift and names of II
, security personnel on shift.
- b. At the and of the shif t the' log will indicate no additional entries and be signed by the Security Shift Supervisor.
i
- c. The oncoming Security Shift Supervisor will acknowledge receipt of the log by his signature.
- 5. All unusual occurrences that take place will be logged by using a short factual statement explaining the occurrence (time, place, personnel, etc.)
- I a. Following is a list of occurrences that would require entry in the log
- ,
- 1) Explicit threats.
- 2) Potential threats.
- 3) Major or moderate loss of physical security effectiveness.
- 4) Non-conformance to Safeguards Plan and procedures.
- 5) Unusual occurrences.
t
- 6. The Security Shift Supervisor will log all unusual occurrences and 4 will perform an evaluation of the occurrence by referring to Security Procedure SP-8 for guidance to determine if the occurrence is a Security Incident and a Security Incident Report is required.
- 7. The Security Shift Supervisor's Log will becreviewed at the first practical time by the Cooper Nuclear Station Security Supervisor and initialed by entry to acknowledge the review.
- 8. The Administrative Services Manager will also review the log periodically and initial pages to acknowledge review.
B. Security Incident Report.
- 1. The Security Shift Supervisor is responsible to initiate a Security Incident Report when an unusual occurrence has been evaluated and determined to be a classified security incident.
- 2. Af ter the incident details are documented on the report, the Security Shift Supervisor reviews the incident with the CNS Security Supervisor and Station management or the Station Shif t Supervisor during non-normal working hours.
Page Of Pages frocedure Nutnher SP-10 Date 8-8-/7,f _ Reviston _0_ 2 _
_3
t
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- 3. The Security Supervisor and Station management or Station Shift Supervisor during non-normal working hours will review the incident report and determine NRC reportability and accordingly will com-plete and sign that section of the report.
- 4. If the incident is NRC reportable, Station management or the Station Shif t Supervisor during non-normal working hours will notify the NRC of the reportable incident in the appropriate time frame. Please refer to Security Procedure SP-8 for specific guidance.
l Revision 0_ Page 3 Of 1 Pages DrcdureNumber SP-10 Date J -g-g 5
SECURITY INCIDENT NEBRASKA PUBLIC POWER DISTRICT REPORT COOPER NUCLEAR STATION Page Of NRC REPORTABILITY: O None D 1 Ilour O 24 IIours Incident Time Incident Date A. Incident Details l i
.k Immediate Corrective Action l 8FCURITY Sil!FT SUPERVISOR DATE C. Action to Prevent Reoccurrence l SECURnY OPERATIONS COORDINA1DR DATE E. Review / Acceptance l REVIE% ED BY DATE ACCEPTED BY DA1T
