Proposed Tech Specs Re Listing of Containment Penetration Conductor Overcurrent Protection DevicesML20151M238 |
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Catawba ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
04/15/1988 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20151M242 |
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References |
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NUDOCS 8804250002 |
Download: ML20151M238 (5) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More 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Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR 1999-09-16
[Table view] |
Text
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s TABLE 3.9-1A (Continued)
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEV!CES SYSTEM POWEREC DEVICE NUMBER & LOCATICN
- 5. 120 VAC Panelboarcs (Continued) 1KPN-2 l Primary Bkr NC Pump Motor 10 Space Heater BacKuo Fuse 1KPN-7-1 Primary Skr Lower Containment Vent Unit Backup Fuse 18 Fan Motor Space Heater 1KPN-8-1 Primary Bkr Lower Containment Vent Unit Backup Fuse 10 Fan Motor Space Haater r#
1KPN-11 Primary Skr Misc Control Power Backuo Fuse for 1ATC 24
- 16. OC Welding Circuits 1EQCB0001 Primary Skr- AA Lower Containment DC Backuo Skr-AB Welding Circuit 1EOCB0002 Primary Skr-AA Upper Containment DC Backup Skr- AB Welding Circuit 1 RPM 8 - 2.,3,ti,5 ge emng 5, I swA gg l
s + n.t M n Wins l
l 8804250002 DR 880415 ADOCK 05000413 DCD l 3/4 8-43 l
CATAWBA - UNITS 1 & 2 I
1 .
TABLE 3.8-18 (Continued)
UNIT 2 CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECT!vE DEv!CES SYSTEM POWEREn DEVICE NUMBER & LOCATION
- 5. 120 VAC Panelboards (Continued) 2KPN-2 Primary 8kr NC Pump Motor 20 Space Heater Backup Fuse 2KPN-7-1 Primary Skr Lower Containment vent Unit Backup Fuse 2B Fan Motor Space Heater 2KPN-B-1 Primary Bkr Lower Containment vent Unit Backup Fuse 2D Fan Motor-593ce Heater 2KPN-11 Primary Bkr Misc Control Power Backup Fuse for 2ATC 24
- 6. OC Welding Circuits x 2EQCB0001 Primary Skr - AA Lower Containment Backup Skr - AB DC Welding Circuit 2EOCB0002 Primary Bkr - AA Uocer Containment Bactuo Skr - AB OC Weiding Circuit L 2f Pf/ 2. ,3,4,s NC Pu.mp Sea.I Sta p,y VenY M betun N}veg A7NnBA - UNIT 5 1 & 2 3/4 B-66
h-O Attachment 2 Discussion and No Significant Hazards Analysis l
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l DISCUSSION AND NO SIGNIFICANT HAZARDS ANALYSIS The proposed amendment would make an addition of one Containment Penetration Conductor overcurrent Protective Device to Table 3.8-1A and one to Table 3.8-1.
These two devices were recently installed via a modification to each of the Catawba units.
l This modification provides remote control from outside containment for reactor coolant pump standpipe drain valves 1NV105, 106, 110, 111, 115, 116, 120 and 121.
The manual valves which controlled the air supply to the above drain valves were replaced with 3-way electric solenoid valves. The control switches for the solenoids are located outside containment (near the reflash panel where the standpipe level alarms are located). Cabling was required from these switches (outside containment) to the solenoids (inside containment) necessitating the addition of the overcurrent protective devices.
The modification was evaluated pursuant *.o the requirements of 10 CFR 50.59 and the analysis showed that the modification would not involve any unreviewed safety questions.
In response to Catawba FSAR question 430.11 a listing of containment electrical penetration classification for Catawba penetrations was provided. The two overcurrent protective devices were added to a penetration which is classified as low voltage - Type G as shown on Figure Q430.ll-7 (attached). The overcurrent protective devices are rated at 20 amps.
10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
The proposed addition of two containment penetration overcurrent protective devices to Tables 3.8-1A and 3.8-1B does not involve a significant increase in the probability or consequences of any previously evaluated accident. The additions are administrative in nature. The modification which added the protective devices was evaluated pursuant to 10 CFR 50.59 and was found to not involve any unreviewed safety questions.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The overcurrent protective devices installed are similar in nature to most of the devices already in use at the plant. No new mode of plant operation is introduced by this modification and the plant is still within the bounds of the safety analysis.
The proposed changes do not involve a significant reduction in any margin of safety. The additions to the Tables are administrative in nature. The modification was evaluated in accordance with 10 CFR 50.59 and was found not to involve an unreviewed safety question.
For the above reasons, Duke Power concludes that this proposed a=endment does not involve any Significant Hazards Considerations.
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