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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure 1999-08-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure ML20134L9151996-10-28028 October 1996 Rev 35 to Swi O-2, Shift Organization,Operation & Turnover ML20151Z9291996-10-15015 October 1996 Rev 0 to 5AWI 6.1.3, Design Change Package,Logs & Records ML20151Z9351996-10-15015 October 1996 Rev 0 to 5AWI 6.1.4, Design Change Description/Safety Assessment ML20151Z9391996-10-15015 October 1996 Rev 0 to 5AWI 6.1.5, Design Change Implementation Plans ML20151Z9071996-10-15015 October 1996 Rev 0 to 5AWI 6.1.1, Design Inputs ML20151Z9601996-10-15015 October 1996 Rev 0 to 5AWI 6.1.9, Design Change Turnover for Operation ML20151Z9751996-10-15015 October 1996 Rev 0 to 5AWI 6.1.10, Design Change Close-Out ML20148P2751996-09-0808 September 1996 Rev 11 to Loss of All Safeguards AC Power ML20141A4141996-05-0808 May 1996 Rev 14 to H4, Offsite Dose Calculation Manual ML20116H8921996-01-0202 January 1996 User'S Guide for Preslock,Gate Valve Pressure Locking Analysis Program Using the Commonwealth Edison Model ML20117F9451995-10-16016 October 1995 Rev 13 to Odcm ML20093J0051995-10-16016 October 1995 Rev 13 to H Procedure H4, Odcm ML20086D6181995-07-0606 July 1995 Rev 1 to PINGP Unit 1 ISI Exam Plan Third Interval 931217- 031216 ML20077A7991994-10-31031 October 1994 Rev 0 to NSP Prairie Island Nuclear Generating Plant Unit 2 ISI Exam Plan Third Interval 941221-201220,2004 ML20079B2391994-10-14014 October 1994 Transco Procedure Tiqap 9.20,For Installation of KM-1 Fire Barrier Systems for Electrical Raceway Systems ML20073D1341994-09-13013 September 1994 Rev 3 to H10.1, ASME Section XI Inservice Testing Implementing Program ML20071Q6431993-12-30030 December 1993 Rev 0 to NSP Prairie Island Nuclear Generating Plant Unit 1 ISI Exam Plan Third Interval 931217-031216 ML20056G1621993-08-20020 August 1993 Rev 2 to Prairie Island Nuclear Generating Plant Units 1 & 2 IST Program Manual ML20096H4411992-05-11011 May 1992 Rev 3 to Prairie Island Nuclear Generating Plant ASME Code Section XI Inservice Insp & Testing Program Second 10-Yr Insp Interval,831216-931216 ML20082B9291991-06-0101 June 1991 Rev 1 to VVP9000520/1, Verification & Validation Plan for Class 1E Qualified Safeguard Load Sequencer ML20056A3391990-07-31031 July 1990 Rev 2 to ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval ML20126C0711990-07-19019 July 1990 Rev 0 to Operations Manual,Section H7.3, Integral Welded Attachment Evaluation Criteria for Prairie Island Nuclear Generating Plant ML20012A3231989-10-0505 October 1989 Rev 11 to Odcm. ML20246P1311989-04-27027 April 1989 Rev 10 to, Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual (Odcm) ML20207L1151988-09-21021 September 1988 Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in As-Built Safety-Related Piping ML20151C4101988-07-12012 July 1988 Rev 0 to Northern States Power Co,Section Ii:Exercise Objectives & Guidelines ML20153B9491988-04-15015 April 1988 Rev 2 to D59, Process Control Program for Solidification/ Dewatering of Radwaste from Liquid Sys ML20196E6481987-09-10010 September 1987 Rev 1 to Process Control Program Manual ML20237L1081987-07-29029 July 1987 Rev 1 to Prairie Island Nuclear Generating Plant,Inservice Insp & Testing Program Manual ML20236J8351987-07-13013 July 1987 Errata to Rev 1 to ASME Code Section XI Inservice Insp & Testing Program Manual,Correcting Administrative Errors Recently Found in 870812 Submittal ML20238A8661987-06-29029 June 1987 Rev 9 to Offsite Dose Calculation Manual ML20209B7361987-01-20020 January 1987 Rev 1 to, Inservice Insp & Testing Program Manual ML20212A0261987-01-13013 January 1987 Rev 8 to Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual ML20207Q4661987-01-0101 January 1987 Rev 20 to Corporate Nuclear Emergency Plan Implementing Procedure, Table of Contents Record of Rev ML20214M0111986-02-14014 February 1986 Rev 6 to Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual ML20206E4191985-08-22022 August 1985 Rev 0 to Corporate Administrative Work Instruction N1AWI 6.1.5, Requisition Contents ML20087D0751984-11-14014 November 1984 Rev 4 to Offsite Dose Calculation Manual ML20107B3951984-10-0808 October 1984 Public Version of Rev 29 to Emergency Plan Inplementing Procedures,Including F3-1, Onsite Emergency Organization, F3-2, Classification of Emergencies, & F3-3, Responsibilities During Notification of Unusual Events ML20097A3381984-08-24024 August 1984 Rev 5 to Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual ML20095L2331984-02-29029 February 1984 Revised Radiation Environ Monitoring Plan ML20080C8711984-02-0303 February 1984 Rev 0 to Emergency Plan Evaluation Exercise 840313,Section Ii:Exercise Objectives & Guidelines ML20087M9501984-01-19019 January 1984 Public Version of Rev 5 to Emergency Plan Implementing Procedure F3-13, Offsite Dose Calculation, Temporary Memo 83-48,Rev 23 to Table of Contents & Jm Felton 840322 Release Memo 1998-08-03
[Table view] |
Text
. . . - - . -_ _ _ .- - . . .
, Enclosure l- ;
L CRITERIA FOR DETERMINING JUSTIFICATION FOR CONTINUED OPERATION WHEN ENCOUNTERING r
i MAJOR DISCREPANCIES IN "AS-BUILT" SAFETY RELATED PIPING !
l SEPTEMBER 21, 1988 1
1 1
ii i
i 4
I 1
l NORTHERN STATES POWER CO.
i 3
j PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1
1717 WAKONADE DRIVE EAST 1
i WELCH, MN 55089 l
1 i
!bk P
A $$ 282 PNU
. s
. TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
& SCOPE................................. 3 2.0 CRITERIA ......................................-..... 3
3.0 CONCLUSION
.......................................... 5
4.0 REFERENCES
.......................................... 5 i
Page 2
- .s
1.0 INTRODUCTION
& SCOPE
- These criteria are in' tended to assure the operability require-ments of safety related piping and associated supports if it is determined that stresses exceed allowables presented in the Prairie Island USAR. These criteria permit operation for an interim period only. Modifications will be made which return the system to within USAR allowables by the next re-fueling outage or sooner if operation permits.
These criteria are intended to expeditiously perform necessary evaluations to determine interim operability and not to delay appropriate actions.
For cases involving components classified as ASME Code Class I where USAR allowables are exceeded, NSP shall be notified upon discovery and NSP shall evaluate reportability require-ments per 10CER50.
2.0 CRITERIA 2.1 Piping Operability Criteria The piping analysis shall be in accordance with ASME,Section III NC-3600 service level D limits (Ref. 1).
The design loading conditions to be applied in the analysis shall include the DBE earthquake. !
i Following is the pipe stress criteria for justifying {
continued operation of the plant i i
(Sgp + SWT
- 3DBE 5 2.0 Sy] (Ref. 1 equation 9) !
Where: S gp = Longitudinal Pressure Stress 1 S WT = Dead Weight Stress ;
SDBE = Stresses Resulting From Design Basis Earthquake Sy
= Material Yield Stress (Reference 1 Appendices) I code Csse N-411 allows for increased damping values, independent of pipe diameter, for seismic analysis.
f Therefore, increased damping values, in accordance with reference 2, will be acceptable when performing these analyses to meet operability. Should the piping stress analysis exceed the value of 2.0 Sy, or pipe supports do not meet their operable limits (see Sect.
2.2), then additional iterative analysis of the piping i
i Page 3
i
. l I
may be required. The iterative analysis may use the knowledge that a support is not capable of withstand-ing the loads, and can be removed from the analysis.
. Where feasible, the actual cupport stiffness may be included in the iterative analysis, along with other
. refinements.
For cases where piping secondary stresses are determined to exceed USAR allowables, a specific case by case approach will be used to determine interim operability.
2.2 Pipe Support & Hanger operability Criteria 4
As a first step in evaluating the support, a linear elastic analysis method will be used to determine the ,
strdss in the support membera. In addition to the loading in Section 2.1, the support loads must include pipe thermal loads and results from free end displace-ment and anchor motion. Supports will be analyzed .
using the allowables listed below to meet operability I requirements. l I
Structural Seeel i'
Tension F t
= 1.20 Sy but 5 0.70 Su i Bending F = 1.20 Sy but b
5 0.70 Su !
Shear Fy = 0.72 Sy but 1 0.42 Su !
Compression F, < F t but not to exceed 2/3 Per ;
Combined Stress For axial compress',on and bending ,
or axial tension and bending, use -l AISC 1.6., (Ref. 6)
Web Crippling = 1.0 Sy [
Weld Stress Fy =
0.42 Su (of weld material) I Anchor Bolts Use Factor of Safety of 2 against ultimate tension and shear values. !
i Snubbers !
Hydraulic Load < manufacturers one time load capacity.
f Movement < total travel Springs Load within catalog range without bottoming out Struts FS = 2 and < 2/3 Per r
- Page 4
__.-_ _ . . _ , , _ . _ _ _ _ _ . _ . _ - ~ _ . . _ _ . . . _ _ _ _ _ . . _
1 All remaining Une manufacturors published fcultsd Catalog Items load rating. Where level D allow-ables are not given, and the factor of safety is specified in the catalog, use design allowables but with FS = 2. (Typical catalog FS = 5, therefore use 2.5 x catalog 1 capacity).
Where F = Allowable Tensile Stress t
F b = Allowable Bending Stress j Fy = Allowable Shear Stress
{
, F, = Allowable Axial Compressive Stress ;
F, = Allowable Weld Stress c
Per = Maximum Strength of Axially Loaded
- . Compression Member ,
i Sy = Specified Minimum Field Strength at Temperature (See Note 1)
Su = Specified Minimum Tensile Strength Temperature FS = Factor of Safety NOTE 1: Actual yield strength may be used where CMTR's are available for the material.
l If a support fails using the linear clastic method, then a more refined analysis may be performed using plastic analysis techniques. The plastic analysis will follow the design rules of ASME Section III, Appendix F, (Ref. 1).
3.0 CONCLUSION
I
, If the above criteria cannot be met, reportability per 10 CFR i
50 must be evalue.ted and system operability requirements per Plant Technical Specifications must be evaluated and appro- ,
priate actions taken.
I 4.0 . REFERENCES f
- 1. American Society of Mechanical Enginee.rs, Boiler and
, Pressure Vessel Codes,Section III, 1983 Edition,
- through Winter 1985 Addenda.
- 2. American Society of Mechanical Engineers, Boiler and
] Pressure Vessel Codes, Case N-411, Dated 9/17/84.
! Page 5 ,
}
i 1
o ,,
. .s s
- 3. NRC-IE Bulletin 79-02, "Pipa Support Bose Plate Danigns Using Concrete Expansion Anchor Bolts," Revision No. 1
, (Supplement No. 1), Dated 8/20/79.
- 4. USAS B31.1.0-1967, Power Piping Code.
- 5. Updated Safety Evaluation Report for PINGP.
- 6. "Manual of Steel Construction," American Institute of Steel Construction, Inc., Eighth Edition, 1980.
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1 I
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