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Results
Other: 05000266/LER-1983-010-03, /03L-0:on 830929,acceptance Test of Fire Detection Sys Found Remote Alarm Function Disabled for Fire Detectors in Auxiliary Feedwater Pump,Vital Switchgear & Cable Spreading Rooms.Caused by Wiring Work, ML19208A635, ML19256F995, ML19262C226, ML19290E879, ML19294C012, ML19309A782, ML19309F407, ML19317H481, ML19318C032, ML19340B145, ML19350C020, ML20002B141, ML20002E093, ML20069Q173, ML20081E499, ML20100R666, ML20112E612, ML20210K148, ML20212F358
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MONTHYEARML19207B4261979-08-0202 August 1979 Forwards Request for Addl Info on Steam Generator Water Hammer to Be Sent to Westinghouse & C-E Licensees,For Plants Not Equipped W/Top Discharge Devices on Steam Generator Feedwater Sys & for Which No Mods Are Planned Project stage: Request ML19208A6351979-08-17017 August 1979 Urges Firm Maint of Schedule for Implementation of All Mods Associated W/General Design Criterion 3 Re Fire Protection. Requests That Any Outstanding Info Re Open Items & Required Design Details Be Submitted on Expedited Basis Project stage: Other ML19209A6611979-10-0101 October 1979 Proposes Changes to Tech Specs of Licenses DPR-24 & DPR-27 Re Fire Brigade Size,In Reponse to NRC 790821 Request.Change Modifies Tech Spec Change Request 46 Project stage: Request ML19290E8791979-11-30030 November 1979 Forwards Recommendations for Fire Protection Design Review Items 3.1.2 & 3.1.23 Re Carbon Dioxide Hose Reel Nozzles & Smoke Exhaust Project stage: Other ML19256G3931979-12-17017 December 1979 Discusses Evaluation of Incomplete Items Identified in 790802 Fire Protection Safety Evaluation.Licensee Submitted Info Re Brigade Shift Size on 791001 & Basis for Staff Assignments on 790821.Proposed Fire Brigade Acceptable Project stage: Approval ML19256F9951979-12-20020 December 1979 Forwards Rept, Fire Detector Location Plan, Mod to Fire Protection Plan.Requests Comment Project stage: Other IR 05000301/19790201979-12-20020 December 1979 IE Insp Rept 50-301/79-20 on 791127-30.No Noncompliance Noted.Major Areas Inspected:Core Power Distribution Limits, Core Thermal Power Evaluation,Power Coefficient of Reactivity Measurement & Rod Drop Time Test Project stage: Request ML19262C2261980-02-0101 February 1980 Forwards Fire Protection Review of Safety Evaluation Items 3.1.12 & 3.2.5.Util Verification of Fire Detector Location Adequate.Util Personnel Qualified to Locate Detectors Project stage: Other ML19294C0121980-02-0505 February 1980 Forwards Info Re Open Fire Protection Issues Review.Encl 1 Summarizes Status of Open Issues.Encl 2 Is NRC Evaluation of Design Description for Proposed Detector Installations.Util 791220 Proposal for Detector Placement Is Acceptable Project stage: Other ML19322E4301980-03-0505 March 1980 Forwards Open Items & Resolution of Incomplete Items for 790802 Fire Protection Program Re Safety Evaluation Rept. Requests Response within 30 Days Project stage: Approval ML19309A7821980-03-26026 March 1980 Forwards Fire Protection Review Items 3.1.17,3.1.25,3.2.2 & 3.2.6.Licensee Proposed Mods to Hydrogen Sys & Reactor Coolant Pump Oil Collection Sys Are Only Partly Acceptable. NRC Should Request Drawings Re Mods Proposed in Item 3.2.2 Project stage: Other ML19309F4071980-04-21021 April 1980 Responds to Re Status of NRC Review of Plant Fire Protection Program.List Re Status of Resolution of Incomplete Items Encl Project stage: Other ML19317H4811980-05-19019 May 1980 Forwards Proposed Rule Entitled, Fire Protection Program for Nuclear Power Plants Operating Prior to 790101. Rule Adds New Section 50.48 & App R to 10CFR50 & Is Expected to Be Published in Fr by End of May Project stage: Other ML19318C0321980-06-23023 June 1980 Forwards Addl Info Re Design of Fixed Water Suppression Sys, Fire Hydrant Insps & Control Room Light Fixtures for Fire Protection Safety Evaluation.Notification Requested by 800718,if Design Mods Are Required Project stage: Other ML19340B1451980-10-13013 October 1980 Forwards Status of Fire Protection Mods Per Amends 39 & 44 to Licenses DPR-24 & DPR-27.Justifications for Schedule Delays Encl Project stage: Other ML20002B1411980-11-18018 November 1980 Forwards Interim 10CFR50.48,suspending Completion Date for Previously Approved Effective Fire Protection Mods,Effective 801029.Rule Will Be Superseded by Pending Revision Project stage: Other ML20002E0931981-01-20020 January 1981 Requests That Completion Date for Fire Protection Mods Be Extended to 811117 to Provide Time Required for Installation of Remote Diesel Generator Panels W/Modified Carbon Dioxide Extinguishing Sys Nozzles & Light Fixture Diffusers Project stage: Other ML19351F8411981-01-22022 January 1981 Forwards Fire Protection Safety Evaluation Suppl,For Proposed Mods Re Revised 10CFR50.48 & New App R.Item 3.1.29 Acceptable.Item 3.1.15 Not Acceptable & Remains Open Item Project stage: Approval ML19351F8441981-01-22022 January 1981 Fire Protection Safety Evaluation Suppl Re Cable Tray Penetration Seal Qualification.Item 3.1.29 Acceptable.Item 3.1.15 Remains Open Project stage: Approval ML19350C0161981-02-13013 February 1981 Approves 810120 Request for Extension of Date to Install Emergency Diesel Generator Remote Panels for Fire Protection Sys.Fire Detector Installation Dates Meet Requirements of 801021 Fire Protection Safety Evaluation.Fr Notice Encl Project stage: Approval ML19350C0201981-02-13013 February 1981 Notice of Extension Until 811117 for Installation of Emergency Diesel Generator Remote Panels for Fire Protection Sys Project stage: Other ML20069Q1731982-12-0303 December 1982 Forwards Review of Util Fire Modeling & Analyses Used to Justify Exemption Requests from 10CFR50,App R Requirements Project stage: Other ML20069M4971983-04-28028 April 1983 Requests Revs to Proposed Mods to 10CFR50 App R Exemption Requests Re Separation Requirements,Per 830322 Meeting & 830325 & 31 Telcons.Detailed Discussion of Revs Encl Project stage: Meeting ML20077D0581983-07-20020 July 1983 Itemizes Clarification of Encl to Re Request for App R Fire Protection Exemptions,Including Revised Description of Proposed Plant Mods to Fire Zones 1-4 Project stage: Request ML20077J3941983-08-0909 August 1983 Suggests Periodic Progress Meetings Re Detailed Description of Alternate Shutdown Capability for Fire Areas & Zones. App R Exemption Requests to Be Submitted by 831027.First Progress Meeting Proposed for 830826 Project stage: Meeting ML20081E4991983-10-26026 October 1983 Forwards Final Rept,Response to 10CFR50 App R `Alternate Shutdown Capability, Supporting Requests for App R Exemptions.Rept Includes Responses to Generic Ltr 81-12 & Evaluation of Component Spurious Operation Project stage: Other 05000266/LER-1983-010-03, /03L-0:on 830929,acceptance Test of Fire Detection Sys Found Remote Alarm Function Disabled for Fire Detectors in Auxiliary Feedwater Pump,Vital Switchgear & Cable Spreading Rooms.Caused by Wiring Work1983-10-28028 October 1983 /03L-0:on 830929,acceptance Test of Fire Detection Sys Found Remote Alarm Function Disabled for Fire Detectors in Auxiliary Feedwater Pump,Vital Switchgear & Cable Spreading Rooms.Caused by Wiring Work Project stage: Other NRC Generic Letter 1984-051984-04-0202 April 1984 NRC Generic Letter 1984-005: Change to NUREG-1201 Operator Licensing Examiner Standards Project stage: Request ML20088A2931984-04-0404 April 1984 Responds to 840326 Request for Clarification of 831026 Submittal Describing Alternate Shutdown Capability (10CFR50,App R).Fire Repairs Not Proposed for Sys Required for Hot Shutdown Project stage: Request ML20084G3171984-04-27027 April 1984 Responds,W/Addl Clarification,To 840423 Request for Addl Info on 10CFR50,App R Re Alternate Shutdown Capability. Proposed Double Break Circuit Mod Will Prevent Spurious Operation of Excess Letdown Isolation Valves Project stage: Request ML20100R6661984-11-27027 November 1984 Forwards Notice of Environ Assessment & Finding of No Significant Impact Re 830517 Application,Supplemented by ,For Exemptions from 10CFR50 App R Requirements Project stage: Other ML20101Q5051985-01-0303 January 1985 Requests Final Resolution of 820630 Request for Exemption from Requirements of App R Through Approval of Proposed Mods.Requests Meeting W/Nrc to Discuss Schedule for Completion of Proposed Mods So Mutual Objectives Can Be Met Project stage: Meeting ML20112E6121985-01-0909 January 1985 Corrects Re Routing of Normal & Alternate Control Power to Safeguards Buses 1-A05 & 1-A06.Errors Discovered in Cable Schedule Used to Perform Evaluation When Compared W/Electrical Elementary Diagrams Project stage: Other ML20129J0531985-07-0303 July 1985 Exemption from 10CFR50,App R,Subsection Iii.G Re Requirements for Fire Protection of Safe Shutdown Capability Project stage: Approval ML20129J0711985-07-0303 July 1985 Notice of Granting of Exemption from 10CFR50,App R, Subsection Iii.G Re Fire Protection Requirements Project stage: Approval IR 05000301/20040301985-08-21021 August 1985 Notice of Violation from Insp on 850301-0430 Project stage: Request ML20134K6751985-08-21021 August 1985 Safety Evaluation Denying Util 820630 Request for Exemption from 10CFR50,App R Re Requirements of Separation of Redundant Trains of Safe Shutdown Capability Equipment in Switchgear Room Project stage: Approval ML20138J1951985-12-11011 December 1985 Forwards Response to Telecopied Request for Info Re 830428 & 1026 App R Exemption Requests Concerning Svc Water Pump Room,Rhr Pump Zones & Auxiliary Bldg Fire Area & Summarizes 851126 Meeting W/Nrc at Facility Project stage: Meeting ML20210K1481986-04-11011 April 1986 Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50,Point Beach Units 1 & 2, Technical Evaluation Rept Project stage: Other ML20215G3211986-10-10010 October 1986 Forwards Addl Info for 860509 Request for Exemption from Certain Requirements of 10CFR50,App R Re Fire Suppression Sys & 3 H Fire Barrier Requirement,Per 860918 Request Project stage: Request ML20212A8251986-12-19019 December 1986 Environ Assessment & Finding of No Significant Impact Re Issuance of Exemption from Technical Requirements of 10CFR50,App.R Project stage: Approval ML20212F3581986-12-31031 December 1986 Exemption to 10CFR50,App R,Section Iii.G Fire Protection Requirements,Per Licensee 830428 Request,As Supplemented by 831026,851211,860509 & 1010 Ltrs & Encl Franklin Research Ctr Technical Evaluation Rept Project stage: Other ML20212F3791986-12-31031 December 1986 Safety Evaluation Supporting Exemption to 10CFR50,App R, Section Iii.G Re Svc Water Pump Room Fire Zone,Rhr Pump Fire Zone & Auxiliary Bldg Fire Area Project stage: Approval 1982-12-03
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Wisconsin Electnc ma comu 231 W. MICHIGAit, P.O. BOX 2046, MILWAUKEE, WI 53201 April 27, 1984 Mr. H.
R. Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555 Attention:
Mr. J.
R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 RESPONSE TO 10 CFR 50 APPENDIX R ALTERNATE SHUTDOWN CAPABILITY POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our April 4, 1984 letter provided clarification of our proposed method to prevent spurious operation of the excess letdown isolation valves for Point Beach Nuclear Plant, Units 1 and 2.
A double break circuit was proposed which would require two separate shorts in two cables in order to allow spurious valve operation.
One short would have to occur between a specific non-energized conductor and a conductor within the same cable or a different cable which is energized at 120 VAC with respect to plant ground.
A second short would also be required between a second specific conductor and plant ground either directly or by short to another grounded conductor.
Although we consider the postulated double short described above to be an incredible event, the following additional clarification is provided in response to an April 23 request by Mr. T. G. Colburn of your staff.
The proposed double break circuit modification is shown on the attached Figure 4-9B.
In the depicted arrangement power to one side of the MOV opening coil is provided via a single conductor cable 1327JD (wire number 0).
This conductor is normally de-energized when the valve is in the closed position.. The other side of the MOV opening coil is connected to plant ground via a single conductor cable 1327JE (wire number X2B).
This conductor is normally isolated from plant ground when the valve is.in the-closed position.
Both of the following must occur to result in the spurious opening of this valve due to a postulated fire.affecting both cables:
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D Mr. H.
R. Denton April 27, 1984 1.
Wire "0" (cable 1327JD) between the control board and the motor control center must short to a conductor of another cable which is energized at approximately 120 VAC.
2.
Wire "X2B" (cable 1327JE) between the control board and the motor control center must short to a conductor of another cable which is connected to plant ground or to plant ground directly.
Cables 1327JD and 1327JE will be a Rockbestos-type "Firezone CRC" cable or equivalent.
Manufacturer's data indicate that this cable maintains an insulation resistance in excess of 10,000 ohms when exposed to-a. direct-2000*F flame as proven by passing the 2000'F gas flame-test with continuing vibration as specified in MIL-W-25038E with the time extended to 60 minutes and the minimum IR increased to-10,000 ohms.
The above description and Figure 4-9B are for the Unit 1 excess letdown valve. -The Unit 2 excess letdown valve wiring will be in the same configuration.
With this configuration the potential for double short occurrence is even less credible than for the original proposed-modification.
In the alternate shutdown scenario, described in our October 27, 1983 submittal, the motor control center which provides power to the excess letdown valves is tripped off within about'15 minutes of fire initiation.
The installation of cable which has been demonstrated to be fire resistant for one hour virtually negates any possibility for spurious letdown valve operation due to a fire causing simultaneous shorts between two different sets of cables.
Should you have additional questions regarding this clarification please contact us.
.Very truly yours, Vice Presid nt-Nuclear Power-C. W. Fay Attachment Copy to NRC Resident Inspector
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