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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] |
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FEBRUARY 1989 ADDENDA O. Date of Issue: February.28, 1989 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR ' STATION INSERVICE INSPECTION PROGRAM FOR ASME CLASS 1, 2, and 3 COMFONENTS Revision 3 This is an addenda to the loose-leaf version of the Inservice Inspect 1'on Program for ASME Class 1, 2, and 3 ~ Components, Revision 3, and are issued 'in the form of replacement or additional pages, revisions, additions, or It is i deletions, and are incorporated directly into- the affected pages.
advisable, however, that these title sheets, and all replaced pages be retained for reference in Tab 13 of the correspondence section.
Summary of Changes:
This is the FIFTH addenda to be published to the Inservice Inspection Program j for ASME class 1, 2, and 3 components, Revision 3.
Replace or insert the pages listed. Changes given below are identified on the pages by a margin note (Feb. 89) next to'the affected area.
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SECTION PAGE(S) DESCRIPTION Augmented Inseevice 1 Updated the number of Inspections types of Augmented ISI.
Added Tab / Type 6 to Summary page.
Augmented Inservice Tab #6, Page 1 Add AISI Type 6 G.E.
Inspections SIL No. 474 Visual ~l Inspections. 1 Correspondence Tab 13 Add Tab 13, Feb. 89, Addenda.
Corresp ndence Tab 14 Add Tab 14, NPPD Response to G.E. SIL No. 474. .;
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AUGMENTED INSERVICE INSPECTIONS Augmented Inservice Inspections (AISI) are not ASME Section XI Code Requirements, but are 1) additional examination areas, or 2) increased inspection f requency or combinations of both which are requested by the Nuclear Regulatory Commission.
Wher. examination components fall into the scheduled testing of ISI and are also AISI requirements, then credit for both requirements may be taken (no double testing).
There are presently six types of Augmented Inservice Inspections required at Cooper Nuclear Station.
TAB TYPE DESCRIPTION 1 1 All ring girder bolting and ring girder anchor bolting is to be volumetrically inspected each ten year interval.
The Anchor Bolting adjacent to the Inboard MSIV is to be visually inspected each ten year interval. (Reference NRC DRO Bulletin #74-3) 2 2 Ultrasonic examination of the feedwater nozzle safe ends, bores, and inside blend radii, liquid penetrant examination of l the feedwater nozzles, and visual inspection of the feedwater O spargers as required per Table 2 and Section 4.3.2.4 of NUREG-0619.
3 3 Visual inspection of the Core Spray Spargers anc' the Core Spray Piping inside the RPV shall be inspected each refueling outage.
(Reference IE Bulletin No. 60-13).
4 4 Ultrasonic Examinations, utilizing G.E. Procedure TP508.0654, Rev. D, or equivalent, are conducted to assess the integrity of the jet pump hold down beams at the mid-length ligament areas bounding the beam bolt. These examinations shall be performed once during the second ten year interval. These examinations may be deferred to the end of the internals.
5 5 Ultrasonic Examinations per G. L. 88-01. G. L. 88-01 applies Oct.SS to all BWR piping made of austentic stainless steel that is four inches or larger in nominal diameter, and contains reactor coolant at above 200*F during power operation regardless of code classification. Tab 5 lists all piping welds not replaced under the scope of G. L. 84-11. Reference Tab 12 of correspondence section. All accessible welds will be examined in accordance with G. L. 88-01.
6 6 Visual inspection of steam dryer drain channel welds during Feb.59 refueling outages. (Reference General Electric SIL No. 474.)
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DATE: 2-2 7'h7 CONTROLLED DOCWENT NUMBER: MM REVISION NUMBER: 3 CONTROLLED DOC NENT TITLE: f3 I [rv9fa* br A585 641.5 d 2 "I3 br*Me YS ORIGINATOR (S): N . A . O c k + li2- RESPONSIBLE MANAGER: 6. M . Ma c e-
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REASON FOR CHANGE: REVIEW SCHEDULE OTHER (S/ t- 4. Y7'/)
EXFLAIN IN DETAIL AND ATTACH NEW DOCUMENT OR REVISION: '/Z e_ Tehr se7 /M9 AdAeuln 4 fer. 3 sF t% .751 favm ; e -
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CATE: 6 'l (ROUTE COMPLETED FORM AND DRAFT TO THE RECORDS CENTER FOR MICR0 FILMING AND FINAL DISPOSITION) ,
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'N I PROCETFcME NU:GER 0.4.1 REVISION NUM3ER 1 PAGE 5 0F 5 l
- ". NEBaASKA PuBuc Powsa DisTaicT l CNSS897101 March 1, 1989 NOTED
{;ite To E. M. Mace MAR 0 31989 FOR INTER-DISTRICT
/ BUSINESS ONLY l From J. R. Flaherty F M. MACE _J Subject _Echruary 1989 ISI Addenda i The subject ISI Addenda is attached for your approval in accordance with CNS l Procedure 0.4.1, "CNS Controlled Documents Other than CNS ecocedure and Vendor i Manuals". l Pending approval, the subject addenda will be transmitted to the owners of record of the ISI Program Documents. The owners of record are as follows:
Set 001 - Vault Copy l Set 002 - R. A. Schultz Set 003 - CNS Quality Assurance Set 004 - NL and S Manager l Set 005 - NRC Copy l
Rocky Schultz will ensure that the vault copy is updated. Two copies will be transmitted to Greg Smith for sets 004 and 005.
Please advise if you have any questions regarding this matter.
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J . R . Flaher t y } ,
Plant Engineering Supervisor JRF: RAS:sa l
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,. ATTACHMENT 3 OPERATING EXPERIENCE REVIEW TRANSMITTAL SHEET l l
DOCUMENT NUMBER: $l L. Oh ; DOCUMENT DATE: jg/h/6g' DATE RECEIVED: //[3/ph-
SUBJECT:
br% Ne w D oih C h.#ct_(RAc Q v REMARKS.
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PLOM f A D hrRE $ WT Co JCC?W en
-m i s $C ROUTE COPY REC 01DfEND INITIATE l TO TO EVALUATE ACTION ACTION q
K Engineering Manager X V M' V Operations Manager
/_ Maintenance Manager I Training Manager !
l Plant Services Manager 1 l
M Outage And Modifications Manager
, K Radiological Manager Other COMMENTS AND RECOMMENDATIONS (Attach Separate Sheet If Hecessary): l l
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.g4y Was A Vendor Manual Change Necessary As A Reb lt Of This OER: Yes !;.t{
If Yes, Provide Vendor Manual Change Request Number:
NOTE: When assigned actions have been completed, return copy of document with this i
1 Transmittal Sheet to the Regulatot'y Compliance Specialist.
Duc Date: 1 Z_/////" '
1 0.10.1 I .~
PROCEDURE NUMBER I
REVISION NUMBER 3 PAGE 9 0 F . 10 *.
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NEBRASKA Puauc Powsn Disraier CNSS888315 November 9, 1988 I
o P. L. Ballinger/J. R. Flaherty FOR INTER-DISTRICT BUSINESS ONLY j From S. L. Bray Subject SIL No. 474 Response l l
Reconsnended Action GE reconnends that BWR owners visually examine steam dryer drain channel welds during refueling outages. If cracks are detected, they should be repaired to j prevent further growth of the cracks. The application of additional weld material to reinforce susceptible areas of existing welds also would reduce the probability of new cracking.
1
Response
The 1989 Outage ISI Program will be augmented to include a visual inspection of the steam dryer drain channel welds. !
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l No further actions are necessary.
S. L. Bra Engineering Specialist Approved by ,
Date OperationsEngipingSupervisor I
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O Powerfy Pride in Nebraska
.. NEBRASKA PuBuc PowsR DisTaicT CNSS888317 November 9, 1988
( P. L. Ballinger/J. R. Flah?rty FOR INTER-DISTRICT l BUSINESS ONLY Front R. A. Schultz Subject 1989 Outage ISI Program I
The 1989 Outage ISI Program will be augmented to include a visual inspection
of the steam dryer drain channel welds. ,
l General Electric recommends a visual examination of steam dryer channel welds during refueling outages. If cracks are detected they should be repaired to prevent further growth of the cracks. This meets the recommendation stated in General Electric SIL 474.
$h R. A. Schultz i ISI/IST Engineer l 1
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