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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. ML17335A3581998-12-0303 December 1998 Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors ML17335A3621998-12-0303 December 1998 Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. 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ML17335A2751998-09-0202 September 1998 Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly. ML17335A1931998-08-28028 August 1998 Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000 ML17335A2731998-08-21021 August 1998 Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package. ML17334A7301998-05-0606 May 1998 Rev 2 of Cook Nuclear Plant Restart Plan. ML17325B5271998-04-0707 April 1998 Rev 1 to Cook Nuclear Plant Restart Plan. ML17334B8041998-04-0303 April 1998 Rev 1 to Valve IST Program for DCP Third 10-Yr Interval. ML17325B5261998-03-0707 March 1998 Rev 0 to Cook Nuclear Plant Restart Plan. 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ML17333A8301997-03-26026 March 1997 Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8331997-03-26026 March 1997 Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 ML20135C3781997-02-24024 February 1997 Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements ML17333A7161996-12-20020 December 1996 Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI ML17333A7151996-12-20020 December 1996 Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys ML17333A5161996-07-22022 July 1996 Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge ML17334B5951996-07-11011 July 1996 Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt ML17333A4771996-06-19019 June 1996 Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05 ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA 1999-09-23
[Table view] Category:TEST REPORT
MONTHYEARML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. ML17331A0531992-09-30030 September 1992 Reactor Containment Bldg Integrated Leakage Rate Unit 1. ML17331A0541992-05-31031 May 1992 Reactor Containment Bldg Integrated Leakage Rate Unit 2. ML17334B3951991-02-22022 February 1991 DC Cook Nuclear Plant Unit 2,Cycle 8 Startup Rept. W/ 910222 Ltr ML19325D6071989-06-30030 June 1989 Reactor Containment Bldg Integrated Leakage Rate. ML17328A1431989-02-28028 February 1989 Reactor Containment Bldg Integrated Leakage Rate,Feb 1989 for DC Cook Nuclear Plant Unit 2. W/890908 Ltr ML17324A5791985-12-0404 December 1985 Reactor Containment Bldg Integrated Leak Rate Test. ML17321A1811984-12-31031 December 1984 Summary of Type B & C Leak Rates, for 1984 ML17321A1821984-06-30030 June 1984 Reactor Containment Bldg Integrated Leak Rate Test. ML20090J5601984-03-23023 March 1984 Reactor Containment Bldg Integrated Leak Rate Test (Preoperational) ML17334A5591983-12-16016 December 1983 Ampacity Test for Power Cables. ML17333A8221983-04-0505 April 1983 Ampacity Test for Power Cables in Randomly-Filled Trays. ML17326A9531982-08-0202 August 1982 Reactor Containment Bldg Integrated Leak Rate Test, 810713-30. ML17324A9211982-02-28028 February 1982 Qualification Test Program for Terminal Blocks,Nuclear Environ Qualification. Supporting Documentation Encl ML17319B0481981-09-10010 September 1981 Reactor Containment Bldg Integrated Leak Rate Test, 810430-0504 ML17320B0881981-07-0707 July 1981 Rept of Test for Seismic & Environ Testing of Mercoid Pressure Switches for American Electric Power Svc Corp. ML17325A8591980-09-0202 September 1980 Qualification Tests of Coaxial-Type Cables in Simulated Steam Line Break & LOCA Environ. ML17321A3401980-04-14014 April 1980 Rev a to Nuclear Environ Qualification Test Rept on Agastat E7000 Series Timing Relays. ML17326A4711979-12-31031 December 1979 Experimental Investigation of Air Entrainment at Reactor Containment Sump Due to Break & Drain Flows. ML19268C0821979-11-19019 November 1979 Dynamic Evaluation Test Program on Safety Injection Sys Panel,Auxiliary Relay Panel & Hot Shutdown Panel. ML20197C9751978-11-14014 November 1978 Reactor Containment Bldg Integrated Leak Rate Test, 780527-29 Covers Acceptance Criteria,Ilrt Test Results,Test Conduct,Instr & Equip Containment Model & Leak Rate Calculations,Ilrtest Prog Printout & Analysis ML17320A5811978-10-26026 October 1978 Seismic Simulation & Radiation Test Program on Seven Pressure Switches. ML17318A5091978-10-26026 October 1978 Seismic Simulation & Radiation Test Program on Seven Pressure Switches. ML20197A4811978-09-19019 September 1978 Startup Test Rept for Subj Facil Describing Startup/Testing Activities:Initial Core Loading,Initial Criticality,Low Pwr Physics Testing & Pwr Ascension Testing Completed Thru 780801 ML20081C0511978-04-10010 April 1978 Reactor Containment Bldg Integrated Leak Rate Test (Preoperational) ML17320A6611975-11-30030 November 1975 Qualified Test of Electric Cables Under Simulated Loca/Dbe by Simultaneous Exposure to Environs of Steam/ Chemical-Spray & Radiation. ML20081C0341975-02-26026 February 1975 Reactor Containment Bldg Integrated Leak Rate Test ML17326B4081970-09-23023 September 1970 Issue 2 to Rept on Test on Limitorque Corp SMB-0-25 Valve Operator. 1999-05-28
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REPORT OF TYPE B AND C LEAK RATES D.C.COOK PLANT UNIT 2-1984 MDTRO INNEf M NPY.(8gg0gq0030 8+<0<~PDR*DOCY 050003i6 P, PDR 0
j TABLE OF CONTENTS SECTION 1.1 2.0 TITLE
SUMMARY
OF RESULTS TABLES 2.1 TABLE 1 2.2 TABLE 2 2.3 TABLE 3 PAGE 2-3 1..0
SUMMARY
OF RESULTS As indicated in the accommanying ILRT report, Type A leakage test results do not indicate a failure to meet the containment overall leakage acceptance criteria.Guideline Type B&C leakages were exceeded, however, as detailed in the following.
Types B&C Leak Rate Testing (**12 THP'4030 STP.203)was performed on Unit 2 between March 12, 1984 and June 29, 1984.Table Ol shows the valves that exceeded their respective guideline leakages.Table 52 gives a brief summary of the repairs made to leaking valves.Table e3 shows a brief history of these valves as tested during previous surveillances.
While testing Zone 4 piping pentrations, several penetrations were found to be leaking.These penetrations were CPN-4, CPN-23, CPN-40,&CPN-44.CPN-4 was repaired by ,welding a hole in the bellows.CPN-23, CPN-40,&CPN-44 also had holes in the bellows but.were not repaired per AEPSC review of the plant FSAR determining that bellows on containment, penetrations are not needed to maintain the leak-tight integrity of containment.
Zone 4 was tested after isolating the above penetrations.
PAGE 1
Volume Description Valve TABLE 1 Guideline (sccm)As Found As Left (sccm)(sccm)Upper Vent.Supply Air Part.Rad.Mon.VCR-105 8 VCR-205 SM-1 3600 60 20019 623 80 109 Nitrogen to PRT N-159 8 N-285 45 565 40 Charging to Regen.Hx RCDT Vent Header RCT Vent Header CLVGCUV Drain Header RHR Recirc'E'ower Cont.Monitor Air Particl Rad.Mon Boron Injection Boron Injection CPN Coils 384 CCW Glycol Return Expan.Post Accident Sample Sup Post Accident Sample Sup CS<<321 DCR-203 8 DCR-207 N-160 8 DCR-201 ,.DCR-620 6 DCR-621 ICM-305 ECR-33 8 ECR-35 ECR-31 6 ECR-32 ICM-251 ICM-250~CCW-243-72 R-157 J ECR-416 ECR-417 180 120 120 120 1080 60 120 240 240 60 60 15 15 23818 297 1639 2407 5910 2495 1300 703 1854 3229 7947 250 299 744 20 258 1907 1243 40 51 120 W L Volume Description Valve Guideline (sccm)As Found As Left (sccm)(sccm)Control Air To Cont.CPN Coils 285 CCW CPN Coils 384 CCW CPN Coils 285 CCW Plant Air to Cont.check Valves Personnel Airlock Cover Flange Zone 4 Piping Pene.XCR-102&XCR-103 CCW-243-'25,>
CCW-244-72 CCR-440 PA"342 N/A N/A 120 60 60 60 120 55 1173 532 109 271 188 3974 121 19853 532 109 271 188 3974 121 802 TABLE 2 During the B&C leak rate testing the following penetrations"'ere found to have excessive leak rates and required repairs: Volume Descri tion Upper Vent, Supply Air Part.Rad.Mon.Nitrogen to PRT Charging to Regn.Hx RCDT Vent Header RCDT Vent Header Valve$j VCR-105&VCR-205 SM-1 N-159&N-285 CS"321 DCR-203&DCR-207 N-160&DCR-201 R~eaiea VCR-105: Xnspected seal&seat, found no damage VCR-205: Manufacturer replaced seal, repaired seat, replaced dowel pin Replaced Valve N-159: Lapped seat, replaced.plug, spring,&gasket N-285: Replaced wedge&gasket Replaced disc&gasket DCR-203: No repair necessary DCR-207: Replaced diaphragm N-160: Cleaned valve disc&seat DCR-201: No repair necessary CLV&CUV Drain Header DCR-620&CR-621 DCR-620: Cleaned seat DCR-621: Cleaned seat, replaced packing 10K Recirc.'E'CM-305 Lapped disc.Lower Cont.Monitor ECR-33&ECR-35 Air Particle Rad.Mon ECR-31&ECR-32 ECR-33: Cleaned&lapped seat ECR-35: Machined seats&repacked valve ECR-31: Iapped plug&seat, replaced gaskets ECR-32: No repairs req'uired Boron Injection Boron Injection CPN Coils 3&4 CCW Glycol Return Expan.ICM-251 XCM-250 CCW-243-72 R-157 Iapped seat Lapped Seat Replaced valve Cleaned seat Post Accident Sample...ECR-416 Sup.a a Lapped&machined seat&plug, replaced gasket PAGE 4
~~4 TABLE TWO (con't.)Volume Descri tion Valve 8 R~eeire Post Accident Sample Sup.Zone 4 Piping Penetrations ECR-417 N/A Lapped seat 6 plug, replaced gasket Welded hole in bellows of CPN-4.CPN-23, CPN-40 and CPN-44 were isolated from the containment penetration and weld channel pressurization system PAGE 5 i~=vi, I, II'C lq TABLE 3 Valve.Guide-~1 ine Mar84-Jun84 Nov82-an8 ar sccm found eft found e t VCR-205&VCR-205 3600 sccm 20019 SCCm 80 Scc sccm Scc 124 12 SM-I N-159&N-285 60 45 623 565 109'0 120 120 501 501 2 40 2 40 CS-321 DCR-203&DCR-207 N-160&DCR-201 DCR-620&DCR-621 180 120 120'20 297 20 16 258 2407 23818 744 16977 06 50 I 2 I 10 61 25 I 8 12 ICM-305 1080 5910 02 02 I 0 I 0 ECR-33&EC R-35 ECR-31&ECR-32 60 120 24 5 I 07 I 00 124 421 421 22 0 I I 40 14 I ICM-25I 240 70 4'0 6 7 ICM-250 CCW-243-72 240 60 I 4 22 120 I 6 2 R-157 60 794 0 ECR-416 15 250 ECR-417 XCR-102&XCR-103 CCM-243-25 15 120 60 532 532 109 109 41 419 1010 0 CCW-244-72 60'71 271 170 4 4 65 1802 CCR-440 PA-342 Airlock Cover Flan.60 120 188 188 974 3974 121 121 21325 0 N A 49.6 4.6 N N Zone 4 Pip~Pe etration 117 802 Page 6
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