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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] Category:TEST REPORT
MONTHYEARML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17352A2061993-08-20020 August 1993 Cycle Xiv Startup Rept. W/930820 Ltr ML17349A6861993-02-18018 February 1993 Reactor Containment Bldg ILRT Rept,1992 Turkey Point Unit 3 Ilrt. ML17348B3491992-01-23023 January 1992 Cycle XIII Startup Rept. W/920123 Ltr ML17348B3601991-10-20020 October 1991 Reactor Containment Bldg Integrated Leak Rate Test (ILRT) Rept - 1991 Turkey Point,Unit 4,ILRT - Date of Test Completion:911020. ML17348A5131990-08-0808 August 1990 Cycle XII Startup Rept. W/900821 Ltr ML17347B2771989-08-21021 August 1989 Cycle XII Startup Rept. W/890821 Ltr ML17347B2911989-05-31031 May 1989 Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Test. ML17347B1571989-03-31031 March 1989 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test. ML17345A6101988-12-19019 December 1988 Flux Map Thimble Tube & Eddy Current Test Rept for NRC Bulletin 88-009. ML17345A1371988-05-0909 May 1988 Rev 1 to Turkey Point Plant Unit 3 Cycle XI Startup Rept. W/880509 Ltr ML20246H9871988-04-30030 April 1988 Environ Qualification of Continental Wire & Cable Corp Instrumentation Cable Installed in Beaver Valley Power Station Unit 1 ML17347A6471987-12-0707 December 1987 Unit 3 Cycle XI Startup Rept. ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20215E4621986-11-30030 November 1986 Voltage Study for Split Group Bus Configuration ML20214L0011986-11-17017 November 1986 Unit 4,Cycle XI Startup Rept ML17342A5951986-03-31031 March 1986 Reactor Containment Bldg Integrated Leakage Rate Test, Types A,B & C Periodic Test,Turkey Point Plant Unit 4. ML20195C7601986-02-20020 February 1986 Rev 1 to Seismic Instruments Channel Check ML20195C7791986-02-20020 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20210T5271986-02-19019 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R140 (HPCS Pump Base Mat) ML20195C7681986-02-18018 February 1986 Rev 1 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C8521986-02-18018 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R130 (HPCS Piping in Reactor Bldg) ML20195C8941986-02-18018 February 1986 Rev 2 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R170 (Reactor Recirculation Piping Support) ML20195C8671986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R180 (HPCS Pump Base Mat) ML20195C8731986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R190 (RCIC Pump Base Mat). Related Documentation Encl ML20195C8601986-02-14014 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R160 (Reactor Bldg Foundation) ML20195C7391986-02-0707 February 1986 Rev 1 to Triaxial Time-History Accelerograph Channel Calibr ML20195C7521986-02-0707 February 1986 Rev 1 to Triaxial Seismic Switch Channel Calibr for D51-N150 ML20213G1521985-09-26026 September 1985 Sanitized Version of Test Program on Isolation Relays & Analog Signal Isolators for Use in Hope Creek Generating Station. W/Three Oversize Drawings ML20133N0211985-08-27027 August 1985 Electrical Cable Separation Verification Testing ML17342A2111985-06-30030 June 1985 Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Test. ML20099E6561985-02-18018 February 1985 Rev 1 to Reactor Vessel Cavity Seal Test Results,Catawba Nuclear Station,Units 1 & 2,McGuire Nuclear Station,Units 1 & 2 ML20112J7191985-02-0404 February 1985 Rev a to Qualification Rept for Model KDI-1000 High-Range Containment Area Radiation Detector & Mineral-Insulated Cable Sys ML20104A9601985-01-18018 January 1985 Reactor Vessel Cavity Seal Test Results ML20198E7441985-01-10010 January 1985 Test Rept for Full Flow Testing of 16,18 & 20-Inch Main Steam Safety Valve Vent Stacks for Yankee Atomic Electric Co ML20137Z8271984-11-30030 November 1984 Nuclear Component Qualification Test Rept Square D 9025-BCW-45 Thermal Switch ML20098F5441984-09-30030 September 1984 Rev 0 to Evaluation of Tests Performed on Energy Absorbing Matl for Pipe Whip Restraints ML20100N1091984-08-31031 August 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 8, Final Rept ML20094C1511984-07-12012 July 1984 Extension of Retainer Lifetime to 4 Cycles ML20094G7451984-04-30030 April 1984 Rev 1 to Evaluation of Energy Absorbing Matl for Pipe Whip Restraints ML20138P4551984-04-19019 April 1984 Elcometer Adhesion Tests Nutec Concrete Coating Repair Sys 11S/1201/11S/1201 11S/1201/11/1201. Related Documentation Encl ML20100N1151984-03-31031 March 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 18, Final Rept ML20090J5601984-03-23023 March 1984 Reactor Containment Bldg Integrated Leak Rate Test (Preoperational) ML20080B2691984-02-29029 February 1984 Diesel Generator Rocker Arm Lube Oil Temp Test Rept - SER Confirmatory Item 26 for Callaway & Item B.26 for Wolf Creek ML20080U4931984-01-31031 January 1984 Evaluation of Natural Circulation Cooldown Test Performed at San Onofre Nuclear Generating Station ML20086P0641983-12-0101 December 1983 Section 5.0, Startup Addenda, to Monthly Project Status Rept ML20080C5391983-10-15015 October 1983 Preliminary Rev 0 to Pre-Core Emergency & Auxiliary Feedwater Sys Test, Test Results Rept for 830503-0703 ML20080C5601983-10-0505 October 1983 Preliminary Rev 0 to Pre-Core Instrumentation Correlation, Test Results Rept for 830516-0701 ML20080C4511983-09-19019 September 1983 Preliminary Rev 0 to Pre-Core Chemical & Vol Control Sys Integrated Test, Test Results Rept for 830604-0704 1999-06-28
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l APPENDIX C Periodic Type B And Tjpe C Test Reports 9
8310310070 830706 PDR FOIA CONNOR83-296 PDR .
CONTAINMENT LEAK RATE TESTS (TYPE B AND C TESTS)
The following routine local leak rate tests were performed during the reporting period on Unit 3; i.e., since the Unit 3 pre-operational ILRT (Type A test).
I. Penetration Tested
- 1. Personnel Air Lock (entire air lock test)
"AS LEFT" Test Date Leak Rate (cc/m) 3/9/73 0.0 7/9/73 0.0 10/30/73 0.0 4/1/74 0.0 '
8/8/74 0.0 12/3/74 8.16 3/20/75 0.0 l 7/9/75 0.0 SH
- 2. Emergency Air Lock (entire air lock test) 3/8/73 0.0 7/10/73 0.0 10/31/73 0.0 4/1/74 0.0 !
8/7/74 61.2 )
, 8/12/74 12.24 12/2/74 20.4 i.
3/19/75 10.*2 7/10/75 0.0
- 3. Fuel Transfer Flange 10/27/73 76.77 12/19/73 0.0 3/23/74 0.0 11/26/74 0.0 11/27/75 78.9
- 4. Equipment Hatch 8/6/73 0.0 10/27/73 0.0 12/18/73 0.0 10/15/74 0.0 11/8/74 0.0
4/10/75 A. _ ,
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- 5. Isolation Valves (after repair)
"AS LEFT" Test Date Lenk Rate (cc/m) 3-873A 8/3/73 21.0 ,
3-873B 8/3/73 0.0 3-873C 8/3/73 28.0 l MOV-86DA, 862A 3/25/74 0.0
{
MOV-880A, 883M 3/25/74 0.0 MOV-880B 6/11/74 0.0 The above tests were performed in accordance with Technical Specification 4.4.2 (Local Penetrations). l 1
II. The local leak rate tests on all boundary valves and penetrations were conducted during the Unit 3 refueling shutdown from October 7, 1974, to December 4, 1974, to meet the refueling surveillance requirements.
The following procedures were used:
Operating Procedure 13514.1 - Personnel / Emergency Air Locks Operating Procedure 13531.1 - Equipment Access Hatches Operating Procedure 13104.1 - Containment Purge Valves Operating Procedure 13404.2 - Electrical Penetration Canisters Operating Procedure 13404.1 - Containment Isolation Valves Operating Procedure 16004.1 - Fuel Transfer Tube Flange The total "as-found" leak rate was 125.67% of the maximms allowed in Section 4.4.2 of - he Technical Specifications.
Repairs and retests were made and the total leak rate at the time of heat up above 2000F was 21.21% of the maximum allowed in Section 4.4.2.
As part of the local leak rate tests, the following valves were repaired to reluce their respective leak rates:
Leak Rate Leak Rate Valv'e Penetration ec/ min. cc/ min.
Repaired Number As-Found As-Left Remarks 989A 8 203 0 Disassembled and cleaned MOV-869 18 216 6.42 Tightened packing 298A 24A 4,826 540 Installed and lapped new plug 298B 24B 3,217 0 Installed and lapped new plug 298C 24C 7,239 0 Installed and lapped new plug MOV-1410 28A 630 0 Cleaned and lapped dise Isolation 28B 450 0 Cleaned and lapped plug Valve B
() POV-2603 36 21,240 1704 Casket leak on body, reduced by caulking
- The following table lists the valves and penetrations tested, with the "as-found" and "as-left" leak rates.
LOCAL LEAK RATE TESTS FOR REFUELING SHUTDOWN IN FALL OF 1974 AS-FOU:iG AS-LEFT Lowest Leak Lowest Leak Penetration Pressure, Pate Pressure Rate g Number Valves Tested ( psia) cc/ min. (psia) cc/ min.
. 1 Mov-750: MOV-751 65.55 540 65.55 540 2 MOV-744A: MOV-744B: MOV-734 70.50 0 70.50 0 3 MnV-716A 71.00 0 71.00 0 3 MOV-716B: 717 77.40 0 77.40 0 3 717 72.10 0 72.10 0 4 MOV-730: 732 70.50 0 70.50 0 5 Valve-A: 517: 549 68.95 0 68.95 0 5 CV-516: 552 70.40 0 70.40 0 6 Check Valve 518 70.60 47.08 70.60 47.08 6 550 69.10 0 69.10 0 7 CV-519 A & B: CV-522A, B, C 67.77 0 67.77 0 8 CV-951: CV-956A 69.85 486 69.85 486 ,
8 989A 66.00 203 67.10 0 9 CV-953: 956B 69.70 0 69.70 0 9 989B 67.80 0 67.80 0 10 4658 A & B 70.20 0 70.20 0 10 Check Valve 4657 71.50 32.1 71.50 32.1 11 MOV-863 A & B: MOV-872: 887 71.45 10.7 71.45 10.7 12 737A 69.30 0 69.30 0 12 738 68.60 0 68.60 0 13 CV-739 : 737B 68.80 0 68.80 0 14 CV-200A, B, C: CV 204 68.20 0 68.20 0 15 Check Valve-312C: CV-310 A & B: CV-311 69.75 21.4 69.75 21.4 HCV-121:'333 '
'15' -
- 68.85> '25.68- 68.85 25.68 %
16 Valve A & B 68.30 0 63.30- 0 .I 17 895 V 69.20 0 69.20 0 18 MOV-866 A &'B: MOV-869 68.50 216 68.10 6.42 19A MOV-880A: 883M 68.50 0 68.50 0 19A Check Valve-890A 66.90 12.85 66.90 12.85 19B MOV-880B: 883N 68.60 0 68.60 0 19B Check Valve-890B 66.00 38.5 66.00 38.5 20 989C: 957A 69.70 27.82 69.70 27.82 ,
20 CV-955 A & B: CV-956C 66.10 53.5 66.10 53.5 1 21 MOV-1417: MOV-1418} 68.55 12.84 68.55 12.84 22 . MOV-1417: MOV-1418) Tested Together 68.55 12.84 68.55 12.84 23 CV-2821: CV-2822 68.50 0 68.50 0 24A 198A 68.00 4826 65.40 S40 24B 298B 68.00 3217 73.80 0 24C 298C 68.00 7239 76.00 0 24A,B,C 297A, B, C 69.50 0 69.50 0 25 MOV-381 69.70 0 69.70 0 28A MOV-1410 64.70 630 70.20 0 28B MOV-1411 65.50 450 70.00 0
- 28C MOV-1412. 68.40 0 68.40 0 29 Check valve-C 70.50 21.4 70.50 21.4 29 CV-2803 71.30 0 71.30 0 31 CV-4659 A & B . 68.60 0 68.60 0 32 Check Valve-B 71.55 21.4 71.55 21.4 32 SV-2912 67.00 450 67.00 450
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r-AS-FOUND AS-LEFT Lowest Leak Lowest Leak Pressure, Rate Pressure Rate Penetration psia ec/ min. psia ec/ min.
Number Valves Tested 67.00 486 67.00 486 33 SV-2911 67.00 450 67.00 450 33 SV-2913 72.40 0 72.40 0 34 Valves A & B 0 65.00 0 35 POV-2600: POV-2601 65.00 65.00 21240 67.30 1704 36 POV-2602: POV-2603 0 74.00 0 CV-855: CV-853A, B, C: HCV-936 74.00 42 0 68.40 0 43 MOV-626: 736 68.40 67.00 2170 67.00 2170
- 47 Valves A & B 0 68.20 0 52 CV-4668 A & B 68.20 ,
69.80 0 69.80 0 l 53 Valves C & D 0 69.20 0 l 54A MOV-860A: MOV-862A 69.20 '
71.00 0 71.00 0 54B MOV-860B: MOV-862B 68.50 0 CV-955C, D, E: CV-956D 68.50 0 55 0 68.40 0 58 Check Valve-873A 68.40 68.40 0 68.40 0 59 Check Valve-873B 69.10 0 69.10 0 60 Check Valve-873C 0 67.30 0 67.30 58,59,60 MOV-843 A & B: 837 71.70 0 71.70 0 61B First Valve Outside Containment 67.60 27.82 CV-2819: CV-2826 67.60 -
27.82 63 66.70 0 66.70 0 64A MOV-1427 MOV-1426 69.70 0 69.70 0 64B 0 MOV-1425 69.40 0 69.40 64C- _ , ^
From ILRT Air Compressor 69.80 'O 69.80 0 65A 0 Pressure Sensing and Flow ILRT 70.60 0 70.60-65B 0 65C ILRT Leakage Flow 69.10 0 69.10 Transfer Tube Flange 66.0 25.7 ,
39 Equipment Hatch 68.7 0 40 Personnel Air Lock, Inner Door 66.7 0 41 8.16 Personnel Air Lock, Outer Door 66.7 41 49 Emergency Air Lock, Inner Door 67.0 0 Emergency Air Lock, Outer Door 65.8 20.4 49 The total leak rate from the electrical canisters equaled zero.
Total As-Found Leak Rate = 43,023.10 cc/ min.
Total As-Left Leak Rate = 7,252.61 cc/ min.
=
l III. Th'e local leak rate tests on all boundary valves and penetrations were conducted during the unit #3 refueling shutdown from October 25, 1975, through December
( 11, 1975. l i.
The following procedures were used; Operating Procedure 13,514.1, Personnel /Emergenty Air Locks Operating Procedure 13,531.1, Equipment Access Hatch Operating Procedure 13,104.1, Containment Purge Valves Operating Procedure 13,404.2, Electrical Penetration Canisters Operating Procedure 13,404.1, Containment Isolation Valves Operating Procedure 16,004.1, Fuel Transfer Tube Flenge The total "as found" leak rate was 546% of the maximum allowed in Section 4.4.2 of the Technical Specifications. .
Repairs and retests were made and the total leak rate at the time of heat-up above 2000F was 27% of the maximum allowed in Section 4.4.2.
A new maximum allowable leak rate was established using La of .25% per day as per Appendix J of 10 CFR 50.
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VALVE REPAIR LIST f
laak Rate cc/m Penetration Valve PWO AS AS Number Number Number FOUND LEFT Remarks t
i 6 518 5872 15,000 195.6 check valve; disassembled and cleaned 8 956A 5873 44,000 21.5 lapped and cleaned 951 10 4657 5871 2,200 38.7 check valve; disassembled and cleaned ,
19t. 890A 34,506 37,000 4,000 check valve; disascembled and cleaned 4
20 CV-955A 34,508 44,000+ 0 lapped and cleaned -
CV-955B I CV-956C ;
28A MOV-1410 34,509 4,000 279.3 lapped and cle:ned !
32 VLV-B 26,789 2,400 6.86 check valve; disassembled and cleaned
~ '
SV-2912 2,600 '301.8' f" 33 SV-2911 8,792 6,900 130.3 replaced valve diaphrams !
SV-2912 1,000 178.4 l' 36 POV-2603 5,897 70,000* replaced shaft seals, bearing and seats 64A MOV-1425 5,870 5,900 0 lapped discs ;
SKVA South 3,600 0 lower left hand insulator was cracked Canister at the base. The entire insulator was replaced. L
- Calculated from pressure drop test.
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LOCAL LEAR RATE TESTS FOR REFUELING SHUTDOUN IN FALL OF 1975 AS-FOUND AS-LEFT Lowest Leak Lowest Leak Penetration Pressure, Rate Pressure Rate Number Equipment Tested psia ec/ min. psia ec/ min.
1 MOV-750: MOV-751 66.0 2500 66.0 2503 2 MOV-744A,B: FCV-605: HCV-75B 65.27 34.4 65.27 34.4 3 MOV-716A 69.43 29.0 69.43 29.0 3 MOV-716B 67.52 37.0 67.52 32.0 3 KC.VLV-717 67.5 15.0 67.5 15.0 4 MOV-730: 732 67.6 30.0 67.6 30.0 5 552:CV-516 70.3 0.0 70.3 0.0 6 CK VLV-518 66.0 15,000 66.0 195.6 7 CV-519A,B: CV-522ABC 68.3 0.0 68.3 0,. 0 8 CV-951:CV956A 66.0 44,000 66.1 21.5 8 989A 68.5 0.0 68.5 0.0 '
9 CV-953:CV-956B 70.07 0.0 70.07 0.0 9 989B 69.32 0.0 69.32 0.0 10 4658 A,B 70.0 0.0 70.0 0.0 10 CK VLV-4657 66.0 2200 67.72 38.7 11 MOV-872 66.89 0.0 69.89 0.0 12/13 737A:739 . 70.0 0.0 70.0 0.0 12/13 CK.VLV-738:737B 71.15 0.0 71.15 0.0 14 CV-200A,B,C 66.0 3500 66.0 3500 14 CV-204 67.78 0.0 67.78 0.0 15 CK VLV 312C 67.53 10.75 67.53 10.75 15 BCV-121:333 70.32 0.0 70.32 0.0 '
16 ' HV-3-1:HV-3-2 69.6 0.0' 69.6 0.0 17 895V 72.11 0.0 72.11 0.0 18 MOV-866A,B:CV-869 69.56 0.0 69.56 0.0 19A MOV-880A 70.1 0.0 70.1 0.0 19A CK.VLV-890A 66.0 37,000 66.0 4,000 19B MOV-880B 68.60 0.0 68.6 0.0 19B CK.VLV-890B 73.55 0.0 73.55 0.0 20 989C 69.43 0.0 69.43 0.0 20 CV-955A,B:CV-956C 66.0 44,000 68.45 0.0
. 21/22 MOV-1417:MOV-1418 68.0 0.0 68.0 0.0 23 CV-2821:CV-2822 67.5 0.0 67.5 0.0 24A -
CK VLV-298A 67.'60 10.0 67.6 10.0 24B CK VLV-298B 70.0 5.0 70.0 5.0 10.0 24C CK.VLV-298C 68.91 10.0 68.91 25 MOV-381 69.6 0.0 69.6 0.0 28A MOV-1410:127 66 0 4,000 66.0 279.3 28B MOV-1411:227 67.2 0.0 67.2 0.0 28C MOV-1412:327 66.2 0.0 66.2 0.0 29 CK VLV-336 65.8 0.0 65.8 0.0 29 CV-2803 68.13 0.0 68.13 0.0 31 CV-4659A,B 68.2 15.0 68.2 15.0 32 CK VLV 'B' 66.0 2400 69.83 6.86 32 SV-2912 66.0 2600 66.0 301.8 33 SV-2911 66.0 6900 66.0 130.3 33 SV-2913 66.0 1080 66.0 178.4 34 203:205 67.95 0.0 67.95 0.0 .
I O
F -
i AS-FOUND AS-LEFT Lowest Leak Lowest Leak Penetration Pressure, Rate Pressure Rate Number Equipment Tested psia ec/ min. psia ec/ min.
L 35 POV-2600:POV-2601 67.5 10.0 67.5 10.0 36 POV-2602:POV-2603 66.0 70,000 70.2 0.0 42 CV-855 68.3 0.0 68.3 0.0 43 MOV-626 69.0 15.0 69.0 15.0 !
64.8 60.0 43 736 64.8 60.0 47 CK VLV 'A' 66.0 279.3 66.0 279.3 52 CV-4668A,B 70.2 0.0 70.2 0.0 53 HV-3-3:HV-3-4 68.5 10.75 68.5 10.75 i 54A MOV-860A:MOV-861A 68.0 0.0 68.0 0.0 l 54B MOV-860B:MOV-861B 68.6 0.0 68.6 0.0 8 55 CV-955C,D,E:CV-956D 69.5 0.0 69.5 0.0 t 58 CK VLV-873A 69.95 0.0 69.95 0.0 59 CK VLV-873B 68.6 0.0 68.6 0.0 60 CK VLV-873C 68.1 30.0 68.1 30.0 58-59-60 MOV-843A,B 67.35 0.0 67.35 0.0 !
61B Valve 'C' 68.6 0.0 68.6 0.0 ,
63 CV-2819:CV-2826 66.0 300.0 66.0 300.0 64A. MOV-1425 66.0 5,900 68.0 0.0 64B MOV-1426 69.05 0.0 69.05 0.0 64C MOV-1427 69.22 0.0 69.22 0.0 65A ILRT 'E' 74.1 0.0 74.1 0.0 j 65B ILRT 'F' 68.0 0.0 68.0 0.0 65C ILRT 'G' 68.4 0.0 68.4 '
0.0
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39 Transfer Tube Flange 66.0 78.9 '
40 Equipment Hatch 70.1 0.0 41 Personnel Air Lock (Inner Door) 70.2 0.0 41 Personnel Air Lock (Outer Door) 66.1 0.0 49 Emergency Air Lock (Inner Door) 68.1 0.0 .
49 Emergency Air Lock (Outer Door) 67.0 0.0 !
The total "AS-FOUND" leak rate for the electrical canisters = 3600 cc/m (the only canister that leaked was 5KV-A2. The lemh was due to a broken insulator which was replaced before heat up)
The total "AS-LEFT" leak rate for the electrical canisters = 0.0 cc/m Therefore, Total "AS-FOUND" leak rate = 245,576.20 cc/m Total "AS-LEFT," leak rate = 12,127.56 cc/m
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