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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
ML20202A9411997-09-25025 September 1997
Rev 0 to PINGP Colr,Unit 1,Cycle 19
ML20135F6611997-03-0303 March 1997
Rev 0 to COLR Unit 2 - Cycle 18
ML20115G8501996-07-12012 July 1996
Non-proprietary Prairie Island Unit 1 Cycle 18 Thimble Deletion Study
ML20100G7161996-02-0707 February 1996
Rev 0 to PINGP COLR Unit 1 - Cycle 18
ML20085G5321995-06-13013 June 1995
Rev 0 to Prairie Island Nuclear Generating Plant COLR Unit 2-Cycle 17
ML20078H3321994-11-10010 November 1994
Rev 1 to Prairie Nuclear Nuclear Generating Plant,Core Operating Limits Rept,Unit 2-Cycle 16
ML20073D5861994-09-15015 September 1994
Startup Physics Testing Rept Unit 1 Cycle 17
ML20072L3041994-08-22022 August 1994
Rev 6 to Pages 184,188,189 & 261 of Prairie Island (PI) Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20058K5151993-12-0808 December 1993
Rev 0 to Praire Island Nuclear Generating Plant Core Operating Limits Rept Unit 2 - Cycle 16
ML20126G5961992-12-30030 December 1992
Rev 0 to Prairie Island Nuclear Generating Plant COLR Unit 1 - Cycle 16
ML20094K0151992-03-10010 March 1992
Rev 0 to Core Operating Limits Rept,Unit 2 - Cycle 15
ML20081L5791991-06-25025 June 1991
Praire Island Nuclear Generating Plant Core Operating Limits Rept Unit 1 - Cycle 15 Rev 0
ML20067E5591991-02-11011 February 1991
Rev 3 to Core Operating Limits Rept Unit 1 - Cycle 14
ML20067E5601991-02-11011 February 1991
Rev 2 to Core Operating Limits Rept Unit 2 - Cycle 14
ML20028G9921990-09-27027 September 1990
Rev 2 to Core Operating Limits Rept Unit 1 Cycle 14.
ML20028G9931990-09-27027 September 1990
Rev 1 to Core Operating Limits Rept Unit 2 Cycle 14.
ML20058L1081990-07-27027 July 1990
Core Operating Limits Rept,Unit 1,Cycle 14,Rev 1
ML20012D9151990-03-22022 March 1990
Rev 0 to Core Operating Limits Rept Unit 1 - Cycle 14.
ML20012D9171990-03-22022 March 1990
Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13.
ML20206U7781986-06-13013 June 1986
Rev 4 to Reload Safety Evaluation Methods for Application to Prairie Island Units
ML20116K1971985-03-31031 March 1985
Nonproprietary Rev 3 to NSPNAD-8102, Reload Safety Evaluation Methods for Application to Prairie Island Units
ML20063E1551982-06-29029 June 1982
LOCA ECCS Limiting Break & Exposure Sensitivity Analysis for ENC XN-1 & XN-2 Reloads at Prairie Island Unit 1 w/5% Steam Generator Tubes Plugged Using ENC Wrem Iia PWR Model
1999-05-13
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pingp.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20216E7151999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with
ML20211D3981999-08-24024 August 1999
Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively
ML20211C2531999-08-0404 August 1999
Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526
ML20210Q4891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with
ML20211B5971999-07-31031 July 1999
Cycle 20 Voltage-Based Repair Criteria 90-Day Rept
ML20209J1131999-07-15015 July 1999
Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20209F9811999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196F4081999-06-23023 June 1999
Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20195G5181999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included
ML20207B5931999-05-26026 May 1999
SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs
ML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
ML20206L6191999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with
ML20205N1081999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with
ML20205Q5101999-03-15015 March 1999
Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229
ML20207J6951999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant
ML20202J7711999-02-0404 February 1999
Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept
ML20202G3761999-01-31031 January 1999
Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units
ML20207L2811999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2
ML20202J1731999-01-22022 January 1999
Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety
ML20206P7861998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With
ML20205H0561998-12-31031 December 1998
Northern States Power Co 1998 Annual Rept. with
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
ML20206N2731998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196D7341998-11-20020 November 1998
Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi
ML20155K6301998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20154H4061998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With
ML20202J7991998-09-30030 September 1998
Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept
ML20198P0571998-09-0303 September 1998
Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator
ML20153B0761998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With
ML20237A3961998-08-11011 August 1998
Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View
ML20237A8171998-08-0505 August 1998
SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2
ML20236X8531998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant
ML20236R6481998-07-15015 July 1998
Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept
ML20236R0771998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant
ML20249A5751998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant
ML20247G7011998-05-31031 May 1998
Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2
ML20248M0561998-05-31031 May 1998
Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique
ML20247E2671998-05-0505 May 1998
Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy)
ML20247G2921998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant
ML20217M6901998-04-29029 April 1998
Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2
ML20216C6361998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2
ML20216H0341998-03-31031 March 1998
Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept
ML20217D2041998-03-13013 March 1998
Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn
ML20236P9801998-03-12012 March 1998
Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys
ML20248L3931998-03-10010 March 1998
ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212
ML20216D0911998-03-0606 March 1998
Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept
1999-09-30
[Table view] |
Text
.
Prairie Island Startup Physics Testing Report Unit 1 Cycle 17
1.0 INTRODUCTION
Forty-eight reload fuel assemblies manufactured by Westinghouse were installed in the Prairie Island Unit 1 reactor during the June 1994 refueling outage. The core design uses the VANTAGE + fuel assemblies enriched to 4.95 w/o U235. For peaking and ITC control this design uses 432 - 6 w/o gadolinium doped pins.
2.0 STARTUP PHYSICS TESTING This report provides test results for the tests conducted during the startup of the Unit 1 Prairie Island Nuclear Generating Plant. The procedures used in the startup test program were the must recent revision reviewed by the Plant Operations Committee. The tests performed included:
a) Zero Power Isothermal Temperature Coefficient b) Control Banks' Worth c) Critical Boron Concentration d) Power Distribution Measurements Table 1 summarizes the data for each test performed.
3.0
SUMMARY
The results shown in Table 1 all fall within the acceptance criteria.
l 94o927o312 94o915 PDR ADOCK 05ooo282 P PDR
TABLE 1 Startup Physics Testing Results Unit 1 Cycle 17 1.0 HZP isothermal Temperature Coefficient Procedure: D32 Revision: 5 (6/25/93)
Test Condition Measured Value Acceptance Criteria ARO +0.7 pcm/ F < 5 pcm/ F 2.0 Control Banks' Worth Measurement j (Using the rod swap method - see report NSPNAD-88408-A, Rev 1,
' Prairie Island Units 1 and 2 Rod Swap Methodology", Sept.1985.)
Procedure: D30 l Revision: 24 (3/22/94) l Test Condition Measured Value Acceptance Criteria Control Bank A 1296.4 pcm 1302 pcm 10%
(reference bank) (1172-1432 pcm)
Control Bank B 412.3 pcm 424 pcm 15%
(360-488 pcm)
Control Bank C 885.6 pcm 908 pcm 15%
(772-1044 pcm)
Control Bank D 804.4 pcm 831 pcm 15%
(706-956 pcm)
Shutdown Bank A 786.3 pcm 801 pcm i15%
(681-921 pcm)
Shutdown Bank B 786.3 pcm 801 pcm i 15%
(681-921 pcm)
Total Banks 4971.3 pcm 5067 pcm i10%
(4560-5574 pcm) 2
- s. e 0 i
+
TABLE 1 (continued) 3.0 Critical Boron Concentration Procedure: D34
Test Condition Measured Value Acceptance Criteria ARO 1878 ppm 1892 + 125 ppm Bank A in, ORO 1728 ppm 1716 i125 ppm 4.0 Power Distribution Measurements j Procedure: SP 1116 Revision: 20 (6/28/94) .
Power Parameter Value Acceptance Criteria 30 % !
Max (RRlm-RRip)/RRip 'l pi 2 0.9 +5.4% 10% ;
pi < 0.9 +5.7 % i15%
FON x 1.03 x 1.05 2.59 <4.80*
FAH x 1.04 1.78 <2.12** !
QPTR 0.984 20.98 and s1.02 ]
-i 4
Acceptance criteria is (2.40/P) x K(z). ,
Acceptance criteria is 1.75 x (1+0.3(1-P)]
{
3 i
)
I
.a 1
~
TABLE 1 (continued)
Power Parameter Value Acceptance Criteria 100%
Max (RRim-RRip)/RRip pj 2 0.9 -3.3% i10%
pi < 0.9 +3.5% i 15%
N 2.11 <2.21 ***
Fo x 1.03 x 1.05 1
FAH x 1.04 1.69 < 1.75**
QPTR 0.988 20.98 and s1.02 Acceptance criteria is 1.75 x (1+0.3(1-P)]
- Acceptance criteria is (2.40/P) x (K(z)/ V(z))
Leaend ARO All Rods Out HZP Hot Zero Power ORO Other Rods Out F
pi Relative Assembly Power P Power l 1
QPTR Quadrant Power Tilt Ratio ,
l RRlm Reaction Rate Integral - Measured RRi p Reaction Rate Integral- Predicted 4
1
!
