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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] Category:TEST REPORT
MONTHYEARLIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20080K2441995-02-13013 February 1995 FCS Unit 1 Simulation Facility Performance Testing Rept LIC-94-0056, Generator Eddy Current Test Rept 1993 Refueling Outage1994-03-18018 March 1994 Generator Eddy Current Test Rept 1993 Refueling Outage ML20067A2641994-01-20020 January 1994 Reactor Containment Building Intergrated Leak Rate Test Rept Nov 1993 Sixth Periodic Test for Fort Calhoun Station Unit 1 ML20127C7981992-08-31031 August 1992 SG Eddy Current Test Rept - 1992 Refueling Outage ML20066E6281991-01-14014 January 1991 Revised 1990 ILRT Rept, Consisting of Table 2 Re Type B & C Penalties for Listed Penetrations LIC-90-0669, Generator Eddy Current Test Rept 1990 Refueling Outage1990-08-30030 August 1990 Generator Eddy Current Test Rept 1990 Refueling Outage LIC-90-0677, Reactor Containment Bldg Integrated Leak Rate Test,Fifth Periodic Test for Mar 19901990-07-25025 July 1990 Reactor Containment Bldg Integrated Leak Rate Test,Fifth Periodic Test for Mar 1990 ML20245C2241989-04-0505 April 1989 Seismic/Isolation Test Rept for GE Relays & Terminal Block, Bussman Fuse Block & Microswitch Selector Switch ML20236L6911987-03-31031 March 1987 Generator Eddy Current Test Rept,1987 Refueling Outage ML20203D4551985-12-31031 December 1985 1985 Refueling Outage Type B & C Local Leak Rate Test Summary ML20097D0991984-09-10010 September 1984 1984 Refueling Outage Type B & C Local Leak Rate Test Summary ML20091C4821984-05-10010 May 1984 Rev 0 to Masonry Unit Wall,Fort Calhoun Power Station ML20074A8281983-05-11011 May 1983 Reactor Containment Bldg Integrated Leak Rate Test,Jan 1983 ML20040E1731981-05-19019 May 1981 Exam of Corroded Studs from Fort Calhoun. ML19331B9161980-07-11011 July 1980 Instrument Error Analysis for Fort Calhoun Containment Leak Rate Test:Jan 1980. ML19318C4381980-06-25025 June 1980 Integrity of Sys Outside Containment Likely to Contain Radioactive Matl. ML19331B9211980-06-11011 June 1980 Reactor Containment Bldg Integrated Leakage Rate Test at Fort Calhoun Station. ML19296B0471980-02-0808 February 1980 RCS Asymmetric Loads Evaluation Program;Interim Rept. ML20245C1931978-06-30030 June 1978 Rev B to Seismic Testing of Spec 200 Current Production Model Rack Mounted Modules in N-2ES Style B Rack 1998-10-27
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INSTRUMENT ERROR ANALYSIS FOR FORT CALHOUN CLRT a
.- January 1980 Prepared for
, 5 Omana Public Pow'er District 1
-_ By i Nuclear Services Corporation 2622 E. 21st.' St. l Tulsa, OK 74114 1
(918)749-2582 Prepared _by: R.L. Novgrod
. Reviewed by:
Approved by: C.B.Noland(,,,d-c C.W. Rowley f ,
July 11, 1980 OMA-0110 T-8068130 -DD . .. - . - - . . . .
l ".
v .
.l" INSTRUMENT ERROR ANALYSIS I. Instrumentation A. Pressure Digital Readout
, Inst # PI-1, PI-2 Mfg Mensor Corp.
Type Bourdon Tube Capsule & Precision Pressure Gage Range 0-100 psia
$ Stability i .002 psi I Repeatability 1 0005 psi Resolution i .001 psi
. Accuracy i .015 psi 1i B. Teiaperature Elements Inst # T-001 through T-030
- Mfg 1 Hy-Cal Engrg
.1 Type 100 0 Platium RTD Range Calibrated for 60 , 85 , and 110 F
- . Repeatability &
4 Hysteresis + 0.1 F Accuracy [0.02F C. Dew Point Measurement System Inst # DPT-31 through DPT-40 Mfg Volumetrics
~
Range Calibrated for 50 , 80 , 100 F -
_. Accuracy 1 00726 psi Repeatability. 1 002 psi Stability (for threedays) 1 00006 psi F,
H D. Readout System i.- Mfg Data logger Model 3000~
accuracy + .19 F + .0024 psi repeatability T .05 F T .0006. psi i stability [.05F 1 0006 psi
E. Flow Measurement System Inst # FI-l Mfg Fisher-Porter
. Model 087-615-588 Calibration .4 to 4 scfm of air 0 60 psig & 80 F Accuracy + 1% of full scale
, c-II. Formula EL = 100 ?p{py+2) +2t py a
~'
where:
EL = error in leakage rate in % by weight per day Ep = pressure instrument error po. inst.
j .. .
= error in total absolute pressure in psia ET =. temperature instrument error no inst.
= error in temperature in 'R Ey = vapor pressure instr 3 ment error no. inst.
= error in water vapor pre-ssure in psia
~
Assuming: ..
~
A. Initial and final temperatures are identical B. Initial and final pressures are identical III. Calculation of E p E =
(repeatability)2 + (resolution)2 + (stability)2 p
- of senors
=
( .0005)2 + ( .001)2 + ( .002)2 2
= 1 6 202 x 10-3 psi 1
L- __
'. e f:
1 IV. Calculation of E T (repeatability)2 , (repeatability of)2 , [ stability of)2 E = f RTD data logger data logger
._. T
- sensors
, (.1)2 + (.05)2 + (.05)2 30 Q
= .02236 F V. Calculation of E y
("E** *ofdetector) + (o*f detector)+ (of readoutrepeatability)2 , (of readou
=
E V
- of sensors
, (.002)2 + (.00006)2 + (.0006)2 + (.0006)2 9
=
J .00072 psi VI. Calculation of E L -
/
Et = 100 2 py)2 =2 +2(ppy)2 2 6
= 100^
2(.00 +2(*0 - 30 +2(.00 2)2= .0068% by wt/ day I
i
?
P I
VII. Calculation of E p Standard conditions for the flowmeters are defined as 14.73 psia and 60 F.
4' = .04 scfm FlowmeterAccuracy=I{00 Flowmeter Error = E F =P 60 T T
- 601.05 x 24 x 100 x .04 x 106 l-80
, 60 + 14.7 76 + 460 80 + 460 x 75.107 .143 x .137 x .04 = .0054 4
1 VIII. Calculation of r /-
E'=EL+Ep = .0068 + .0054 = .0122% by wt/ day o
N 2
em k
L m
W W
t
,