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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] Category:TEST REPORT
MONTHYEARML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20078M9041994-11-23023 November 1994 Quad-Cities Nuclear Power Station Unit One Cycle Fourteen Startup Test Results Summary ML20078B9221994-10-20020 October 1994 Reactor Containment Bldg Integrated Leak Rate Test,Quad- Cities Nuclear Power Station,Unit 1,940723-24 ML20059G0031993-10-29029 October 1993 Revised Quad-Cities Nuclear Power Station Unit 2 Cycle 13 Startup Test Results ML20056F7161993-08-24024 August 1993 Quad-Cities Nuclear Power Station,Unit 2 Cycle 13 Startup Test Results Rept ML20056F0621993-08-19019 August 1993 Quad-Cities Nuclear Power Station,Unit 1 Cycle 12 Startup Test Results ML20056F0631993-08-19019 August 1993 Quad-Cities Nuclear Power Station,Unit 2 Cycle 12 Startup Test Results ML20046B5781993-05-19019 May 1993 Reactor Containment Bldg Integrated Leak Rate Test Quad- Cities Nuclear Power Station. ML20044C0631993-03-0909 March 1993 Cycle 13 Startup Test Rept Summary. W/930309 Ltr ML20102A6931992-07-23023 July 1992 Quad-Cities Nuclear Power Station,Unit 2,Cycle 12 Startup Test Results ML20099H0521992-04-0606 April 1992 Reactor Containment Bldg Integrated Leak Rate Test, Quad-Cities Nuclear Power Station Unit II for Period 920401-06 ML20085A9551991-07-19019 July 1991 Quad-Cities Nuclear Power Station Unit 1 Cycle 12 Startup Test Results ML20077G7941991-03-0202 March 1991 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20011F5141990-02-26026 February 1990 Quad-Cities Nuclear Power Station Unit 1 Cycle 11 Startup Test Results. W/900226 Ltr ML20011E7161990-02-0606 February 1990 Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station Unit 1,891114-15. ML20055C8591989-10-31031 October 1989 Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept ML20045H5641989-09-19019 September 1989 Equipment Qualification Rept for Moore,Isolator,Moore Signal Transmitter & Marathon Fuse Block,CWE-3840,890919. W/930713 Ltr ML20206F4641988-11-16016 November 1988 Reactor Containment Bldg Integrated Leak Rate Test, 880612-13 ML20205H1071988-10-19019 October 1988 Cycle 10 Startup Test Results ML20153G0421988-06-13013 June 1988 Reactor Containment Bldg Integrated Leak Rate Test ML20150C1541987-12-0606 December 1987 Reactor Containment Bldg Integrated Leak Rate Test ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20238E2911987-06-25025 June 1987 Rev 0 to Irradiation Study of Boraflex Neutron Absorber, Interim Test Data ML20205K1401987-03-26026 March 1987 Quad-Cities Nuclear Power Station Unit 2 Cycle 9 Startup Test Results ML20210C8591986-10-15015 October 1986 Reactor Containment Bldg Integrated Leak Rate Test, Quad-Cities Nuclear Power Station,Unit 2,861014-15 ML20199F1321986-06-17017 June 1986 Quad-Cities Nuclear Power Station Unit 1 Cycle 9 Startup Test Results ML20197A7621986-03-23023 March 1986 Reactor Containment Bldg Integrated Leak Rate Test, Quad-Cities Nuclear Power Station,Unit 1,860322-23 ML20134N7871985-08-28028 August 1985 Quad-Cities Nuclear Power Station Unit 2,Cycle 8,Startup Test Results ML20135F1211985-05-28028 May 1985 Reactor Containment Bldg Integrated Leak Rate Test, for 850526-28 ML20108A4921984-11-0808 November 1984 Cycle 8 Startup Test Results ML20100N1091984-08-31031 August 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 8, Final Rept ML20107F0991984-07-24024 July 1984 Reactor Containment Bldg Integrated Leak Rate Test, Quad-Cities Nuclear Power Station,Unit One,840724-27 ML20084N0341984-05-0808 May 1984 Cycle 7 Startup Test Results ML20100N1151984-03-31031 March 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 18, Final Rept ML20084F7091984-02-10010 February 1984 Reactor Containment Bldg Integrated Leak Rate Test ML20082V2381983-12-13013 December 1983 As-Found Type B & C Local Leak Rate Test Results for Unit 1 During Last Three Refueling Outages ML20071A8371983-02-17017 February 1983 Quad-Cities Nuclear Power Station,Unit 1,Cycle 7 Startup Test Results ML20028F1151983-01-20020 January 1983 Reactor Containment Bldg Integrated Leak Rate Test, Quad-Cities Nuclear Power Station,Unit One,821216-17. ML20042A6411982-03-15015 March 1982 Quad-Cities Nuclear Power Station Unit 2,Cycle 6 Startup Test Results. ML19341D6711981-04-0303 April 1981 Quad-Cities Nuclear Power Station,Unit 1,Cycle 6 Startup Test Results. ML19318B6651980-06-19019 June 1980 Cycle 5 Startup Test Results. ML19321B1711980-03-12012 March 1980 Reactor Containment Bldg Integrated Leak Rate Test. ML19257D1571979-12-31031 December 1979 Quad-Cities Nuclear Power Station Units 1 & 2 Secondary Containment Leak Rate Test Summary, Per Tech Specs Section 6.6.C.3 ML19225A5521979-07-0505 July 1979 Reactor Containment Bldg Integrated Leak Rate Test, 790219-22 ML19263D2101979-03-0606 March 1979 Secondary Containment Leak Test Rept.Concludes Standby Gas Treatment Sys Maintains 1/4 Inch of Water Vacuum in Secondary Containment Bldg Under Calm Conditions W/Flow Rate No Higher than 4,000 Cfm ML17187A8031969-05-16016 May 1969 Cavitation Test Rept 12x14x14-1/2 Cvds Pump. 1998-09-24
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4 TIP Reproducibility and Core Power Symmetry l 3 -!
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- 4. Core Power Distribution Symmetrv Analysis l Purcose I The purpose of this test was to determine the magnitude of indicated l core power distribution asymmetries using data (TIP traces and OD-1) collected in conjunction with the CMC update. ;
Criteria l A. The total TIP uncertainty (including random noise and geometric uncertainties obtained by averaging the uncertainties for:all data ~ .
sets) must be less than 9%. l I
B. The gross check of TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%. ;
Results and Discussion j Core power symmetry calculations were carried out based upon computer l program OD-1 data run on August 19. 1993 and again on October 9. 1993. ;
The average total TIP uncertainty from the two symmetry calculations was !
2.985%. The random noise uncertainty was 1.427%. This yields a !
geometrical uncertainty of 2.621%. The total TIP uncertainty was well !
within the 9% limit.
The above results were performed without using LPRM strings 5 and 33.
String 5 is a Hydrogen Water Chemistry (HWC) probe in which the "D" level LPRM detector has been replaced by HWC detectors. A safety !
evaluation (93-27) was performed for this change and no unreviewed i 3
safety questions were indicated. The effect on the 0D-79 program will i be that 1 symmetric pair of LPRMs will be unavailable for the core ;
symmetry calculation, namely pairs 48-09 and 08-49 (strings 5 and 33. l respectively). These are peripheral strings and will have the effect of - i decreasing the core symmetry calculation' total uncertainty. This effect '
occurs because the power magnitude on the periphery is smaller than the a power magnitude in the center of the core. Thus. a' differential change hetween the peripheral pair power levels will result in a greater percent uncertainty than a differential change in the power level of :
center core symmetric pairs. Data was taken in order to support this :
l from a Unit 2 tip set done in December 1992 with only 39 strings run. ,
With no other failures present, the core symmetry calculation will meet i its acceptability requirements.
Table 1 lists the symmetrical TIP pairs and their respective deviations. l Figure 2 shows the core location of the TIP pairs and their TIP l readings. The maximum deviation between symmetrically located TIP pairs )
occurred during the October 9.1993 run and was 9.611% for pair 9-20.
This is well within the 25% limit.
1 STMGR 01293 GGC 3
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. The method used to obtain the uncertainties consisted of calculating the
. average of the nodal ratio of TIP pairs by: I n 22 1 I I Rij
_R = 18n j=1 i=5 .
where Rij is the ratio for the ith node $f TIP pair j. there being n j such pairs, where n=18.
Ncxt the standard deviation of the ratios is calculated by: j n 22 i I I (Rij - li)2 1/2 !
o= i=1 i=5 j R (18n - 1) :
o, is multiplied by 100 to express o as a percentage of the ideal value n i of op of 1.0. l
% a, - o, x 100 The total TIP uncertainty is calculated by dividing % on by V 2 in order '
to account for data being taken at 3 inch intervals and analyzed on a 6 l' inch nodal basis.
In orde- to calculate random noise uncertainty the average reading at' i each node for nodes 5 through 22 is calculated by:
1 MT NT I I BASE (N. M. K) l BASE (K) - NT x MT M=1 N=1 where NT = number of runs per machine = 5 '
MT = number of machines - 5 l BASE (K) = average reading at nodal level K. j K = 5 through 22 1 i
The random noise is derived from the average of the nodal variances by:
22 MT NT f 1/2 I I I BASE (N. M. K) - BASE (K)
% o noise - K=5 M=1 N=1 BASE (K) x 100 18 (NT x MT -1) l
.- 1 Finally the TIP geometric uncertainty can be calculated by:
% a geometric = (% o total2- % o noise?) 1/2 STMGRiO!293.GGC 4 l
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. Table 1 l CORE SYMMETRY i Based on OD-1 From i The Avera9e Between the 8-19-93 Case ci and the 10-9-93 Case '
SYMMETRICAL TIP AVERAGE- ,
PAIR NUMBERS ABSOLUTE DIFFERENCE % DEVIATION i a-b f= T-T 3 % = 100 X T/((T, + T3 )/2)- ,
1-6 1.9$ 2.12 2-12 7.16 5.71 l 3-19 ' 57
. 1.20- -;
4-26 0.86 0.66 :
8-13 2.11 1.59 9-20 9.46 7.61 !
10-27 0.68 0.50 1
11-34 5.81 4.26 i 15-21 3.14 2.66 .
16-28 2.22 1.95 !
17-35 18-39 6.18 4.60 4.54 5.27 l '
- . 23-29 0.30 0.24 !
2 24-36 0.54 0.42 !
25-40 1.24 1.21 31-37 1.91 1.43 ;
32-41 1.40 2.28
'i 22 Average Deviation - 3.0029 ;
T = I T,(K) /18 3 :
i=5 l
Not used due to Hydrogen Water Chemistry Probe in-core location 48-09 (string 5). The "D" level detector does not exist, so the TIP could not be run in index. Thus OD-79 core symmetry could not be calculated.
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