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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 ML20076N2861983-07-13013 July 1983 Forwards Application for Amend to License NPF-3.Amend Revises Tech Specs Re Operability Requirements of DHR Sys in Mode 3,revs to Radiological Effluent Tech Specs & Rev to Table 4.11-1 for Consistency Project stage: Request ML20076N3151983-07-13013 July 1983 Proposed Changes to Tech Specs Re Operability of DHR Sys in Mode 3,revs to Radiological Effluent Tech Specs & Rev to Table 4.11-1 to Make Notation Consistent W/Std Radiological Effluent Tech Specs Project stage: Request ML20076N3071983-07-13013 July 1983 Application for Amend to License NPF-3,revising Tech Specs Re Operability Requirements of DHR Sys in Mode 3,revs to Radiological Effluent Tech Specs & Rev to Table 4.11-1 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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R FeDruary1,1983 O}b DISTRIBUTTnN C Docket File.)
NRC PDR L PDR Docket No. 50-346 ORB #4 Rdg DEisenhut OELD AE0D Mr. Richard P. Crouse EJordan Vice President, Nuclear JTaylor Toledo Edison Company ACRS-10 Edison Plaza ADe Agazio 300 Madison Avenue RIngram Toledo, Ohio 43652 Gray File EBlackwood
Dear ifr. Crouse:
H0rnstein StmJECT: DECAY llEAT DEMOVAL CAPABILITY REDUNDANCY On June 11, 1980, the f!PC requested that you amend the /,pendix A Technical Specifications for your facility with respect to provisions for decay heat renoval capability to provide for redundancy in all operational nodes. He enclosed, for your cuidance, nodel Technical Specifications which would provide
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an acceptable resolution of this issue.
Toledo Edison Company subnitted an application, Iten 3, Toledo Edison Company letter dated December 26,1980 (flo. 669), to anend the Davis-Besse Facility Operatino License in response to our request. 11e have reviewed the application and find that your proposed changes to the Technical Specifications follow our model Technical Specifications closely for all nodes of operation except for node 3.
Your proposed Specification 3.4.1.2, applicable in nodes 3, 4, and 5, would provide for decay heat renoval redundancy by requiring at least two of the following loops to be operable:
1.
Reactor Coolant loop 1 and associated stean generator l
2.
Reactor Coolant Loop 2 and associated steam generator l
3.
Decay Heat Renoval Loop 1 4
Decay Heat Renoval loop 2 It is further specified that at least one of the above loops nust be in operation.
As presently proposed, Specification 3.4.1.2 would pernit operation in node 3 with one reactor coolant loop and associated stean generator in operation and the renaininq reactor coolant loop inoperable provided at least one decay heat renoval loop is operable.
In node 3, RCS pressure and temperature can far exceed the design conditions of the Decay Heat Renoval Systen, 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 node 3.
Please submit a nodification to your proposed anendnent to assure the required redundancy, or axplain how redundancy, when in node 3, is assured by your current proposal.
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( NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY usam --sas-seo
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i fir. Richard P. Crouse Please provide your response no later than 45 days from the date of this letter. This request for infornation affects fewer than ten respondents; therefore, 0"8 clearance is not required pursuant to P.L.96-511.
Sincerely,
- v.ii G IIL Q 3; g gI:D S Y J0M P. STOL Johr) F. Stolz,ZaChief e
Operating Reactors Branch #4 Division of Licensing cc: See next page i
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y Toledo Edison Company ccw/ enclosure (s):
Mr. Donald H. Hauser Esq.
U.S. Nu, clear Regulatory Comission The Cleveland Electric Resident Inspector's Office Illuminating Company 5503 N. State Route 2 P. O. Box 5000 Oak Harbor, Ohio 43449 Cleveland, Ohio 44101 Gerald Charnoff, Esq.
Shaw, Pittman, Potts and Trowbridge-1800 M Street, N.W.
Washington, D. C.
20036 Paul M. Smart, Esq.
Fuller & Henry 300 thdison Avenue
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P. O. Box 2088 Regional Radiation Representative Toledo, Ohio 43603 EPA Region V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois Babccck & Wilcox 60604 Nuclear Power Generation Division 7910 Woodmont Avenue, Suite 220 Bethesda, liaryland 20814 Ohio Department of Health ATTN: Radiological Health Program Director P. O. Box 118 President, Board of County Columbus, Ohio 43216 Comissioners of Ottawa County Port Clinton, Ohio 4',452 Attorney General Department of Attorney General 30 East Broad Street Columbus, Ohio 43215 Harold Kahn, Staff Scientist Power Siting Comission 361 East Broad Street Columbus, Ohio 43216 Mr. James G. Keppler, Regional Adninistrator U. S. Nuclear Regulatory Commission, Region III T
799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Larry D. Young Managtr,i:uclear Licensing Tole @ Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 l