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MONTHYEARML19318A4791980-06-0505 June 1980
Forwards Response to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Review Described in Encl 1 Revealed Error. Decay Heat Pump Suction Was Not Isolated by Containment Isolation Actuation as Stated in Page 2
Project stage: Other
ML20126D8351980-06-11011 June 1980
Ltr to All Operating PWRs Requesting Amend to Tech Specs Re Decay Heat Removal Capability.Amend Is Necessary to Provide Permanent long-term Assurance That Redundancy Will Be Maintained
Project stage: Other
ML19318C4301980-06-26026 June 1980
Forwards Addl Info Re Shift Manning,Licensing,Testing of Power Operated Relief Valve Isolation Sys,Automatic Trip of Reactor Coolant Pumps & Small Break LOCA Methods,In Response to NRC
Project stage: Other
ML19330B7881980-07-25025 July 1980
Notice of Issuance & Availability of Amend 28 to License NPF-3
Project stage: Other
ML19330B7851980-07-25025 July 1980
Amend 28 to License NPF-3,revising Tech Spec Setpoint for Automatic Closure of Decay Heat Removal Sys Isolation Valves & Implementing Pressurizer Heat Interlock
Project stage: Other
ML19337B6211980-09-23023 September 1980
Notifies That Fire Protection Mods Should Be Completed at End of Current Refueling Outage.Requests Revision of Fire Protection Tech Specs within 60 Days.Fire Protection STS Encl
Project stage: Other
ML20151B3601980-12-26026 December 1980
Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization
Project stage: Request
ML20009C8881981-07-10010 July 1981
Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2
Project stage: Other
ML20009C8841981-07-10010 July 1981
Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs
Project stage: Request
ML20009C8871981-07-10010 July 1981
Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors
Project stage: Request
ML20028G3531983-02-0101 February 1983
Forwards Model Tech Specs for Proposed Amend to App a Tech Specs Re DHR Capability Redundancy.Mod Requested to Assure Redundancy in Mode 3.Response Requested within 45 Days. W/O Encl
Project stage: Other
ML20069E4511983-03-17017 March 1983
Forwards Explanation on How DHR Redundancy Assured in Mode 3 Operation,In Response to NRC .Tech Specs Will Be Revised to Include Applicable Limits by 830513
Project stage: Other
ML20023D5501983-05-13013 May 1983
Advises That Due to Difficulties W/Rev,License Amend Request Re DHR Capability Redundancy Will Be Submitted by 830615
Project stage: Other
ML20024C2131983-07-0808 July 1983
Proposed Changes to Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization
Project stage: Request
ML20024C2111983-07-0808 July 1983
Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization
Project stage: Request
ML20024C2081983-07-0808 July 1983
Forwards Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization.Fees Previously Submitted w/801226 Amend Request
Project stage: Request
ML20082F1661983-11-22022 November 1983
Requests Expeditious Issuance of Amend to License NPF-3,per 801223 Application & 810710 Supplemental Submittal Re Fire Barrier Penetrations,Tech Spec (Item 6)
Project stage: Supplement
ML20136J2191985-12-10010 December 1985
Discusses Plans Re Exemption Requests Provided in 840906 App R Compliance Assessment Rept & Application to Amend License NPF-3 Re Fire Protection Tech Specs.No Further Action on Exemption Request Required.Application Withdrawn
Project stage: Request
1981-07-10
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TOLEDO
%ms EDISON Docket No. 50-346 N$ce saw License No. NPF-3 Serial No. 917 March 17, 1983 Mr. John F. Stoltz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
Dear Mr. Stolz:
This is in response to your letter dated February 1, 1983, relating to the Decay Heat Removal Capability Redundancy. You have requested Toledo Edison to provide you with an explanation on how the decay heat removal redundancy is assured in mode 3 operation. Attachment I provides Toledo Edison's response to your letter as relating to the Davis-Besse Nuclear Power Station Unit 1.
Very truly yours,
/Yf RPC:FYC:HA cc: DB-1 NRC Resident Inspector 00/
8303220058 830317 PDR ADOCK 05000346 P
PDR THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
Docket No. 50-346 License No. NPF-3 Serial No. 917 March 17, 1983 Page 2 ATTACHMENT 1 TO TOLEDO EDISON LETTER TO THE NRC ON DECAY HEAT REMOVAL CAPABILITY REDUNDANCY Concern:
Toledo Edison Company submitted an application, Item 3, Toledo Edison Company letter dated December 26, 1980 (No. 669), to amend the Davis-Besse Facility Operating License in response to our request. We have reviewed the application and find that your proposed changes to the Technical Specifications follow our model Technical Specifications closely for all modes of operation except for mode 3.
Your proposed Specification 3.4.1.2, applicable in modes 3, 4, and 5, would provide for decay heat removal redundancy by requiring at least two of the following loops to be operable:
1.
Reactor Coolant Loop 1 and associated steam generator 2.
Reactor Coolant Loop 2 and associated steam generator 3.
Decay Heat Removal Loop 1 4.
Decay Heat Removal Loop 2 It is further specified that at least one of the above loops must be in operation.
As presently proposed, Specification 3.4.1.2 would permit operation in mode 3 with one reactor coolant loop and associated steam generator in operation and the remaining reactor coolant loop inoperable provided at least one decay heat removal loop is operable.
In mode 3. RCS pressure and temperature can far exceed the design conditions of the Decay Heat Removal System, therefore, Specification 3.4.1.2 does not appear to provide for the required redundancy for the reactor coolant loop operation when the unit is in mode 3.
Please submit a modification to your proposed amendment to assure the required redundancy, or explain how redundancy, when in mode 3, is assured by your current proposal.
Response
Toledo Edison Company has revieued your concern that in mode 3 Reactor Coolant System (RCS) pressure ri temperature can exceed the design conditions of the Decay Hen F. nv.tl System. We concur with your comment and will submit an app? b a c, ar your approval to amend the Technical Specification for Davic-sssJs it 1, so that the applicability of Section 3.4.1.2.a will be modet 4 anc ;, and in mode 3 when both the RCS pressure is less than 330 psig and RCS temperature is less than 350*F.
J
Dock t No. 50-346 License No. NPF-3 Serial No. 917 March 17, 1983 Page 3 Tech. Spec. Section 3.4.5 shall be applicabic in modes 1 and 2, and in mode 3 when either RCS pressure is greater than 330 psig or the RCS temperature is greater than 350*F.
Appropriate sections of the Technical Specification will be revised to reflect this change by May 15, 1983.
se e/8
