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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 REPORT
MONTHYEARML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20073D5011994-08-20020 August 1994 Reactor Containment Building Integrated Leak Rate Test, June 1994 ML20063L7261994-02-22022 February 1994 Startup Physics Test Rept Unit 2 Cycle 16 ML20199A0491994-01-0909 January 1994 Issue B to FTCR/94/0060, Test Rept for 1 Hour Fire Hose Stream Tests on Darmatt KM1 Fire Protection Sys for Electrical Circuits Sys to ASTM E119 NRC GL 86-10 Suppl 1 ML20044C3221993-01-31031 January 1993 Reactor Containment Bldg Integrated Leak Rate Test. ML20082T4801991-08-20020 August 1991 Reactor Containment Bldg Integrated Leak Rate Test,June 1991 ML20244B6821989-06-0707 June 1989 Startup Physics Test Rept,Unit 2,Cycle 11 ML20245G1381989-04-30030 April 1989 Unit 2 Reactor Containment Bldg Integrated Leak Rate Test ML20235V2971987-06-30030 June 1987 Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency ML20137K3641986-01-20020 January 1986 Reactor Containment Bldg Integrated Leak Rate Test Rept, Oct 1985 ML20128N2701985-01-15015 January 1985 Generator Tube Repair Using Leak-Tight Sleeves, Final Rept ML20199A0031984-04-10010 April 1984 Rept on Fire Resistant Cables, for Rockbestos Co,New Haven,Ct ML20039D6051981-11-17017 November 1981 Inservice Inspection - Exam Summary Prairie Island Nuclear Generating Plant - Unit 1,810908-1014,Refueling Outage 6, Insp Period 3. ML20008F8161981-05-0707 May 1981 Startup Physics Test Rept,Unit 2,Cycle 6. ML20004E1391981-03-31031 March 1981 Reactor Containment Bldg Integrated Leak Rate Test,Mar 1981. ML20003B4881981-02-0404 February 1981 Auxiliary Feedwater Pump Endurance Test. ML20002E3861981-01-22022 January 1981 Startup Physics Test Rept Unit 1 Cycle 6. ML19347C7341980-10-31031 October 1980 Unit 1 Reactor Containment Bldg Integrated Leak Rate Test - Oct 1980 ML19341A9931980-10-22022 October 1980 Analysis of Failed Steam Generator Support Bolts from Northern States Power Co,Prairie Island Nuclear Generation Plant,Unit 1. Attachment a to Parameter,Inc Rept IE-121 Encl ML19338G6211980-06-30030 June 1980 Fire Qualification Test on Retrofit Penetration Seals. ML19309H6421980-03-11011 March 1980 Startup Physics Test Rept,Unit 2,Cycle 5 Startup. ML19247B0221979-08-0101 August 1979 Cycle 5 Startup Physics Test Rept. 1998-10-08
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.Prairis Island V Stercup Physics Tact Raport Unit 1 Cycle 6 1.0 Introduction The Prairie Island Unit I reactor had 40 reload fuel assemblies maaufactured by Exxon Nuclear Company installed in 1980 during the fif th refueling for <. hat facility.
2.0 Startup Physics Test - Introduction Reference 1 identified the startup related tests conducted for the Unit 1 Cycle 5 startup. Tests described in detail with analytical results in that report included the following:
(a) Zero Power Isothermal Temperature Coefficient (b) Control Banks' Rod Worth (c) Critical Boron Concentration (d) Boron Worth (e) Power Distribution Measurements This report provides test results for the above tests conducted during the startup of Prairie Island Nuclear Generating Plant, Unit 1. The procedures used in the startup test program were the most recent revision reviewed by the Plant Operations Committee.
3.0 Startup Physics Tests - Results Table 1 summarizes the following data for each test performed.
(a) Test (b) Procedure / Effective Revision (c) Parameter (d) Measured Value (e) Acceptance Criteria 4.0 Summary The data presented in Table 1 shows acceptable agreement with the acceptance criteria.
The Quadrant Power Tilt Ratio (QPTR) was larger than expected. Power waa limited to 50% while extensive analysis was performed to identify the cause of the tilt. No single definitive cause was ident ified .
Safety concerns of the larger than expected QPTR were reviewed in depth. The intent of limiting the QPTR to 1.02 is to continuously, radially, monitor the flux shape to limit the core peaking factors. Since core peaking factors were recently directly measured using incore measurement and all peaking f actors were well within their limits, no safety concerns exist.
Following discussions between Exxon and the NRC Staff, Core Performance Branch, power was increased to 90% and then 100%. Incore flux maps were taken at both power levels.
Additional incore maps continued to show peaking factors well within their limits. The excore nuclear instruments were calibrated. The tilt is being monitored by additional flux maps to ensure a stable predictable flux shape.
5.0 Reference (1) Letter, L 0 Mayer (NSP) to J G Keppler (NRC) dated August 1, 1979.
8101270(ltg"]f
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v Table 1 Unit 1 Cycle 6 Startup Test Results 1.0 HZP Isothermal Temperature Coefficient Procedure: D32 Revision: 1 (9/6/79)
Test Condition Measurede Acceptance Criteria 1so ARO -2.67 pcm/F <0 pcm/F 2.0 Control Banks' Worth Measurements Prodecure: D30 Revision: 2 (7/24/80)
Test Condition Measured Worth Acceptance Criteria Control Bank D 768 pcm 778 pcm + 15%
Control Bank C 1377 pcm 1371pcm][15%
Control Bank B 772 pcm 878 pcm + 15%
Control Bank A
~
1639 pcm 1636pcm}[15%
All Control Banks 4556 pcm 4663 pcm j; 10%
3.0 Critical Boron Concentration ,
Procedure: D34 Revision: 1 (9/6/79)
Test Condition Measured Value Acceptance Criteria All Rods Out 1411 ppm 1403 j; 50 ppm D+C+B+A In 886 ppm 840 j; 50 ppm 4.0 Differential Boron Worth Procedure: D30 Revision: 2 (7/24/80)
Test Condition Acceptance Criteria Measuredd{
<All Control Banks > -8.7 pcm/ ppm -8.2 pcm 10%
p pm --
l
- 5.0 Power Distribution Marnuriments Procedure
- Spill 6 Revision: 5 (9/12/80)
Plant Condition Parameter Value Acceptance Criteria HZP, ARO MAX (RRIm -RRIp )/RRI p Pi > 0.9 -7.3% + 10%
Pi T 0.9 8.7% 7 15%
N v,
9 Maximum 2.33 at z = 8.3f t <4.16 at z =8.3ft Limiting 2.32 at z = 9.0ft <4.12 at z =9.0ft F ** 1.56 <1.86 kn QPTR*** 1.044 <1.02 48% Power MAX (RRIm -RRIp )/RRI p Pi > 0.9 -4.6% + 10%
Pi I'0.9 3.8% 7
__ 15%
F **** 1.88 at z = 7.3ft <4.20 at z =7.3ft Q
F g 1.50 <l.71 QPTR 1.026 <1.02 99% Power MAX (RRIm -RRIp )/RRI p Pi > 0.9 -4.5% + 10%
Pi T 0.9 4.4% 115%
F 9 Maximum 1.75 at z = 5.9f t <2.17 at z = 5.9ft Limiting 1.74 at z = 7.3ft <2.12 at z = 7.3ft F
bH 1.47 <1.55 QPTR 1.019***** <1.02
- Values include uncertainties of 1.05.
Criteria is 2.145 x K(z)/P.
- Values include uncertainties of 1.04.
Criteria is 1.55 [1 + 0.2(1-P) } (1-REP (BU)] .
- The excore nuclear instruments had not been calibrated at th is t ime . The value shown is from incore instruments which are not limited by the Technical Specifications.
- The limiting and maximum occurred at the same axial location.
- Additional Maps taken in the same period indicated QPTR's from 1.017 to 1.0208.
O
-Legend HZP Hot Zero Power i ARO All Rods Out RRI m
Reaction Rate Integral - measured RRI Reaction Rate Integral - predicted P
Pi Relative assembly power QPTR Quadrant Power Tilt Ratio M iso isothermal temperature coefficient pcm/ F '
db boron worth pcm/ ppm
<All Control Banks > average value overall control banks i
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