Topical Rept Evaluation of Addendum 1 to NEDO-10466A, Power Generation Control Complex Design Criteria & Safety Evaluation. Rept Acceptable for Referencing in License Applications,Subj to Listed ConditionsML20128H297 |
Person / Time |
---|
Issue date: |
05/17/1985 |
---|
From: |
NRC |
---|
To: |
|
---|
Shared Package |
---|
ML20128H254 |
List: |
---|
References |
---|
NUDOCS 8505300487 |
Download: ML20128H297 (2) |
|
Similar Documents from NRC |
---|
Category:TEXT-SAFETY REPORT
MONTHYEARML20217M1641999-10-19019 October 1999 Safeguards Evaluation Rept Accepting Amend 29 to License SNM-33 for Abb Combustion Engineering Nuclear Power,Inc ML20217N1731999-10-0808 October 1999 Safeguards Evaluation Rept Approving Amend 11 to License SNM-1097 for GE Re Rev 5 to Physical Protection Plan ML20217B3951999-10-0606 October 1999 Compliance Evaluation Rept Supporting Amend 3 to Coc GDP-1 ML20217C3831999-10-0404 October 1999 Safety Evaluation Supporting Amend 60 to License SNM-696 ML20216J4711999-09-29029 September 1999 Safety Evaluation Rept Supporting Amend 36 to License SNM-1168 for Framatome Cogema Fuels ML20203D0991999-09-18018 September 1999 Integrated Materials Performance Evaluation Program Review of Maine Agreement State Program, 980915-18 ML20216E7881999-09-15015 September 1999 Safety Evaluation Supporting Amend 1 to License SNM-0362 ML20211G9151999-08-31031 August 1999 External Regulation of Department of Energy Nuclear Facilities.A Pilot Program ML20212M2271999-08-31031 August 1999 Monthly Status Rept on Licensing Activities & Regulatory Duties of Nrc ML20217K6091999-08-30030 August 1999 Draft Rept, Integrated Materials Performance Evaluation Program Review of Washington Agreement State Program, 990830-0903 ML20211B4431999-08-19019 August 1999 SER Accepting Amend 28 to License SNM-33 for Abb Combustion Engineering Nuclear Power,Inc ML20211B4201999-08-19019 August 1999 SER Supporting Amend 10 to License SNM-1097 for GE ML20217G3201999-08-17017 August 1999 Draft, Integrated Materials Performance Evaluation Program Review of Iowa Agreement State Program, for 990817-20 ML20217L8271999-08-17017 August 1999 Proposed Final Rept, Integrated Materials Performance Evaluation Program Review of Iowa Agreement State Program, 990817-20 ML20210T7881999-08-12012 August 1999 Safeguards Evaluation Rept Accepting Amend 58 to License SNM-0696 for General Atomics ML20210T8431999-08-12012 August 1999 Safety Evaluation Supporting Amend 59 to License SNM-0696 ML20210U0091999-08-12012 August 1999 Safety Evaluation Supporting Amend 7 to License SNM-1067 ML20212M2331999-08-0303 August 1999 Staff Response to Tasking Memorandum & Stakeholder Concerns, as of 990803 ML20217M9361999-07-31031 July 1999 Nuclear Regulatory Commission 1998 Annual Report ML20211F4771999-07-31031 July 1999 Monthly Status Rept on Licensing Activities & Regulatory Duties of Nrc ML20210L5681999-07-30030 July 1999 SER Accepting Renewed License SNM-142 for Purdue Univ ML20210E9991999-07-23023 July 1999 SER Accepting Amend 57 to License SNM-696 for General Atomics ML20210E9681999-07-23023 July 1999 SER Accepting Amend 17 to License SNM-1227 for Siemens Power Corp ML20210R2011999-07-16016 July 1999 Draft Rept, Integrated Materials Performance Evaluation Program Review of South Carolina Agreement State Program 990712-16 ML20216E0011999-07-13013 July 1999 Final Rept, Impep Review of North Dakota Agreement State Program,990413-16 ML20210H6911999-07-0606 July 1999 Final Rept Impep Review of Maryland Agreement State Program,990322-26 ML20211F4921999-07-0202 July 1999 Staff Response to Tasking Memorandum & Stakeholder Concerns as of 990702 ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196K3791999-06-30030 June 1999 Annual Rept on Effectiveness of Training in Nuclear Industry for Cy 1998 ML20210L4731999-06-30030 June 1999 Monthly Status Rept on Licensing Activities & Regulatory Duties of USNRC, Dtd June 1999 ML20212G6821999-06-25025 June 1999 Baseline Insp Program Workshop on 990621-25 in Irving,Tx. with Significance Determination Process Workbook ML20195K4001999-06-16016 June 1999 Draft Technical Study of SFP Accidents for Decommissioning Plants ML20210K0441999-06-15015 June 1999 Draft Rept Impep Follow-up Review of Kansas Radiation Control Program on 990615-17 ML20212K0161999-06-15015 June 1999 Final Rept, Integrated Materials Performance Evaluation Program (Impep) Follow-Up Review of Kansas Radiation Control Program ML20195D3151999-06-0202 June 1999 SER Approving Amend Request Re Changes to Emergency Plan ML20210L4891999-06-0202 June 1999 Staff Response to Tasking Memo & Stakeholder Concerns, as of 990602 ML20195D0281999-06-0202 June 1999 Safeguards Evaluation Rept Approving Request for Time Extension to Rept Results of Physical Inventory ML20209F7421999-05-31031 May 1999 Monthly Status Rept on Licensing Activities & Regulatory Duties of Usnrc ML20195B6871999-05-24024 May 1999 Safety Evaluation Supporting Amend 2 to License SNM-986 ML20207A2961999-05-19019 May 1999 Integrated Materials Performance Evaluation Program Review of Region III Materials Program, 990315-19,proposed Final Rept ML20206L5541999-05-11011 May 1999 Safety Evaluation Approving Amend to Include as Authorized Activity,Storage of Moderated Special Nuclear Matl in sea-land Containers Equipped with Storage Grids Fastened to Floor ML20206Q9751999-05-10010 May 1999 Draft Rept, Integrated Materials Performance Evaluation Program Review of North Dakota Agreement State Program, 990413-16 ML20209G1931999-05-0303 May 1999 Staff Response to Tasking Memo & Stakeholder Concerns as of May 3 1999 ML20207C0411999-04-30030 April 1999 Monthly Status Rept on Licensing Activities & Regulatory Duties of Us Nrc ML20195B7861999-04-30030 April 1999 TER for Proposed Remedial Action at Naturity Uranium Mill Tailings Site Naturita,Co ML20210R5421999-04-28028 April 1999 Final Rept, Integrated Materials Performance Evaluation Program (Impep) Follow-Up Review of New York City Radiation Control Program ML20205R2891999-04-12012 April 1999 Safety Evaluation Approving Change to Authorized Use & Place of Use for Matl Specified in Condition 6.H ML20205P5591999-04-0909 April 1999 Safety Evaluation Rept Approving Amend Request Dtd 990312, Re Changes to Mailing Addresses ML20206B5101999-04-0707 April 1999 Draft Supporting Statement for 10CFR26 Fitness-For-Duty Program ML20207C0571999-04-0505 April 1999 Staff Response to Tasking Memo & Stakeholder Concerns as of 990405 1999-09-29
[Table view]Some use of "" in your query was not closed by a matching "". Category:TOPICAL REPORT EVALUATION
MONTHYEARML20249A2201998-06-10010 June 1998 SER Accepting Licensing TR BAW-10221P, NEMO-K,Kinetics Solution in Nemo ML20059E3071990-08-31031 August 1990 Safety Assessment of Yaec 1735, Reactor Pressure Vessel Evaluation Rept for Yankee Nuclear Power Station. Detailed Plan of Action W/Listed Elements Requested within 60 Days After Restart to Demonstrate Ability to Operate Longer ML20059A2291990-08-17017 August 1990 Evaluation of Topical Rept Cen 387-P, Pressurizer Surge Line Thermal Stratification. Info Provided in Ref 1 & 2 Inadequate to Justify Continued Operation for 40-yr Plant Life ML20059B9861990-08-13013 August 1990 Partially Withheld Topical Rept Evaluation of Cen 387-P, Pressurizer Surge Line Flow Stratification Evaluation. Rept Found Inadequate to Justify Continued Operation for 40-yr Plant Life ML20059A7731990-08-0909 August 1990 Review of B&W Owners Group Pressurizer Surge Line Thermal Stratification BAW-2085 Analysis Per IE Bulletin 88-011 ML20056A7331990-08-0606 August 1990 Generic SER Re Mark III Containment Hydrogen Control ML20055J2191990-07-25025 July 1990 Safety Evaluation Re Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratifiction Evaluation. Rept Found Inadequate ML20056A3341990-07-25025 July 1990 Partially Withheld Topical Rept Evaluation of CEN-387-P, Pressurizer Surge Line Flow Stratification Evaluation. Rept Considered Inadequate to Justify Continued Operation for 40-yr Plant Life ML20055H0921990-06-25025 June 1990 Topical Rept Evaluation of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation ML20055D3041990-06-21021 June 1990 Review of C-E Owners Group Topical Rept Cen 387-P Re Pressurizer Surge Line Flow Stratification.Info Provided by C-E in Refs 1 & 2 Not Adequate to Justify Continued Operation for 40-yr Plant Life ML20210V1461987-02-11011 February 1987 Topical Rept Evaluation of Rev 1-P,Suppls 3 & 4 to CEN-203-P, Post-Test Analysis of Semiscale Test S-UT-8. Rept Acceptable for Ref in License Applications ML20214T8591986-11-28028 November 1986 Topical Rept Evaluation of Addendum 1 to WCAP-10054, Addendum to Westinghouse Small Break ECCS Evaluation Model (WCAP-10054) Using Notrump Code for C-E Nsss. Rept Acceptable for Ref in License Applications ML20215D1001986-10-0101 October 1986 Topical Rept Evaluation of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification Vol II (Vipre). Rept Acceptable for Ref for Haddam Neck Licensing Calculations of Core Thermal Hydraulics Using VIPRE-01 ML20210V0831986-09-30030 September 1986 Topical Rept Evaluation of WCAP-7908, FACTRAN-A Fortran IV Code for Thermal Transients in UO2 Fuel Rod & App.Rept Acceptable ML20210V0901986-09-26026 September 1986 Topical Rept Evaluation of XN-NF-85-92(P), Exxon Nuclear U Dioxide/Gadolinia Irradiation Exam & Thermal Conductivity Results. Rept Acceptable for Licensing Applications W/ Listed Restrictions ML20210V1031986-09-26026 September 1986 Topical Rept Evaluation of Suppl 4 to XN-75-27(P), Exxon Nuclear Neutronics Design Method for Pwrs. Rept Acceptable for Calculating Neutronic Characteristics of PWR Cores W/Up to 8 W/O Gadolinia Bearing Fuel Rods ML20210G4021986-09-23023 September 1986 Topical Rept Evaluation of WCAP-10858, AMSAC Generic Design Package. Generic Design acceptable.Plant-specific Details Require Approval ML20206Q0601986-08-25025 August 1986 Topical Rept Evaluation of Addendum 3 to Rev 1 to WCAP 9561, Thimble Modeling in Westinghouse ECCS Evaluation Model. Changes Meet Requirements of 10CFR50.46 & 10CFR50,App K & Acceptable ML20203J6181986-07-31031 July 1986 Topical Rept Evaluation of Rev 1 to XN-NF-82-06(P), Qualification of Exxon Nuclear Fuel for Extended Burnup. Rept Acceptable ML20202G2621986-07-0808 July 1986 Topical Rept Evaluation Accepting Exxon Nuclear Co Large Break ECCS Evaluation Model,Exem/Pwr,For Ref in License Applications ML20199G8381986-06-23023 June 1986 Topical Rept Evaluation of WCAP-10965, Advanced Nodal Code: Westinghouse Advanced Nodal Computer Code. Code Acceptable in Predicting Core Reactivity & Coefficients & Core Power Distribution for Design & Safety Analyses ML20210S1701986-05-0505 May 1986 Topical Rept Evaluation of Rev 2 to XN-NF-74-5, Description of Exxon Nuclear Plant Transient Simulation Model for PWRs (PTS-PWR). Rept Acceptable ML20204A3211986-05-0101 May 1986 Topical Rept Evaluation of EPRI NP-2511-CCM,Vols 1-4, VIPRE-01:Thermal Hydraulic Analysis Code for Reactor Cores. Rept Acceptable for Referencing in License Applications ML20199D3491986-03-18018 March 1986 Topical Rept Evaluation of BAW-1875, B&W Owners Group Cavity Dosimetry Program. Rept Acceptable for Referencing in License Applications ML20154B0911986-02-20020 February 1986 Topical Rept Evaluation of TR-UR-85-225, ASEA-ATOM Control Rod Blades for Us Bwrs. Rept Acceptable for Ref in License Applications ML20141E3211985-12-26026 December 1985 Topical Rept Evaluation of XN-NF-81-51(P) LOCA Seismic Structural Response of Exxon Nuclear Co BWR Jet Pump Fuel Assembly. Rept Acceptable for Referencing in Applications ML20141E9651985-12-26026 December 1985 Topical Rept Evaluation of XN-NF-696, Exxon Nuclear Co Solution to Sample Problems-PWR Fuel Assemblies Mechanical Response to Seismic & LOCA Events. Rept Acceptable for Referencing in License Applications ML20138N6161985-12-16016 December 1985 Topical Rept Evaluation Conditionally Accepting Suppls 1-3 of Rev 2 to XN-NF-79-71, Exxon Nuclear Plant Transient Methodlogy for Bwrs ML20138R9001985-11-0505 November 1985 Topical Rept Evaluation of Amend 11 to Rev 6 to NEDE-24011-P-A, GE Std Application for Reactor Fuel (Gestar Ii).Rept Acceptable for Referencing in Licensing Applications ML20198B5381985-10-30030 October 1985 Topical Rept Evaluation Accepting Rev 1 to CENPD-199-P, C-E Setpoint Methodology Submitted on 820413 for Referencing in Licensing Submittals ML20205E8791985-10-28028 October 1985 Topical Rept Evaluation of WCAP 10456, Effects of Thermal Aging on Structural Integrity of Cast Stainless Steel Piping for Westinghouse Nsss. Proposed Model May Be Used to Predict Cast Stainless Steel Matl Embrittlement Heat ML20138P1191985-10-28028 October 1985 Topical Rept Evaluation of WCAP-10665-P, Ex-Core Axial Power Monitor. Algorithms & Calibr Processes Acceptable. Addl Operational Info Required for Burnup Correlation Matrix ML20134F7521985-08-13013 August 1985 Topical Rept Evaluation of Rev 3 to CENPD-255-A, Class 1E Qualification - Qualification of Class 1E Electrical Equipment & Amend 9 to CESSAR Chapter 3.Qualification Program Adequate & Conforms to NRC Requirements ML20134D2321985-08-13013 August 1985 Topical Rept Evaluation of NEDE-22148-P, Extended Burnup Evaluation Methodology. Criteria & Analysis Methods Acceptable ML20126K6141985-07-18018 July 1985 Topical Rept Evaluation of WCAP-1044, Vantage 5 Fuel Assembly. Rept Acceptable for Referencing in License Applications.Licensees Required to Perform plant-specific Safety Analyses ML20129C0151985-07-0303 July 1985 Topical Rept Evaluation of ATC-8019-P, Atcor AVRS-80 Vol Reduction Process Sys. Rept Acceptable Ref in License Applications for LWRs ML20133E2651985-07-0303 July 1985 Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 Re Small Break LOCA Evaluation Model CRAFT2 (Rev 3).CRAFT2 in Compliance W/Evaluation Criteria of 10CFR50,App K ML20128G5801985-06-27027 June 1985 Topical Rept Evaluation of BAW-10092(P),Rev 3 & BAW-10154(NP), CRAFT2- Fortran Program for Digital Simulation of Multinode Reactor Plant During Loss of Coolant. Repts Acceptable ML20128H2971985-05-17017 May 1985 Topical Rept Evaluation of Addendum 1 to NEDO-10466A, Power Generation Control Complex Design Criteria & Safety Evaluation. Rept Acceptable for Referencing in License Applications,Subj to Listed Conditions ML20128D0001985-05-0909 May 1985 Page Changes Clarifying 850301 Topical Rept Evaluation of Rev 6 to Amend 7 to NEDE-24011-P, GE Std Application for Reactor Fuel. Rept Acceptable for Referencing in License Applications ML20128A9881985-05-0909 May 1985 Topical Rept Evaluation of NS-NRC-85-3025, Sser on BART-A1 Computer Code Input Methodology Mod. Rept Acceptable for Referencing in License Applications Under Limitations Delineated ML20244D1711985-01-18018 January 1985 Topical Rept Evaluation of WCAP 10456, Effects of Thermal Aging on Structural Integrity of Cast Stainless Steel Piping for Westinghouse Nsss. Cast Stainless Steel Piping Sys Initially Less Fracture Resistant than Base Metal ML20211D9461983-06-27027 June 1983 Evaluation of Rev 0 to Interim Technical Rept 6, Interim Technical Rept on Diablo Canyon Unit 1 Independent Verification Program Auxiliary Bldg. NRC Agrees That Further Expansion of Rept Re Seismic Model Unnecessary ML20211D5761983-02-15015 February 1983 Staff Rept Evaluation of Rev 0 to Interim Technical Rept 32, Interim Technical Rept on Diablo Canyon Unit 1 Independent Verification Program PG&E Pumps. Rept Revealed Deficiences in PG&E Design Analyses 1998-06-10
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
-
ENCIDSURE s
Safety Evaluation Report GE Tcpicai Report, NE00-10466A Adddender i Fower Generation Control Ccrplex Introduction-In Revision 2 of NED0-10466A dated March 1978, General Electric reccmmended that a Halon 1301 fire extinguishing system would be required to protect the PGCC. The system would provide a 20 percent concentration cf Halen 1301 for a soak time for 20 minutes for deep seated fires. The staff found it acceptable.
By letter dated Februtry 28, 1986, General Electric submitted Addendum 1 to -
NEDO-10466A. General Electric requested deviations that wculd reduce the Halon 1301 concentration to be prov.ided to protect the PGCC and the amount of soak time required. For PGCC's with 80 percent or greater Tefzel cable, General Electric requested that the concentration and soak time of Halon 1301 be changed to be surface burning fire concentration and soak time, i.e., 6
- ercent for 10 minutes.
Discussion / Evaluation s - Based on testing anc research performed on cable insulation since 1978, Genera 1 Electric.has reevaluated deep seated fires occurring in the PGCC.
General Electric indicates that Figure 4.2 of NEDO-10466,' Revision 2, Appendix F, shows that the rate and degree of burning of the Tefzel cable used in the PGCC essentially corresponds with that of the ignition source.
Because of this, the key to limiting the severity of burning of Tefzel is in the capability of-extinguishing the ignition source. If the ignition source is extinguished, the fire in the Tefzel will self-extinguish, almost simulta-neously. Tefzel is a thermoplastic material, which reans that as its temper-ature is raised it will melt before it burns, that is, the auto ignition temperature is higher than-its melting temperature. This characteristic of melting.before it burns ensures that burning can occur only at its surface as a liquic.
c.
8505300487 850517 PDR TDPRP ENVGENE.
C PDR-
+ ...
2 Tne st'rface burning cFaracteristic of Tefzel have been substantiated in every fire' test. conducted by General Electric.
V Afte? reviewing the' test results in Appendix F of NEDO-10466A, we agree with General Electric that Tefzel cable will exhibit surface burning characteristics and not deep seated. -Therefore, the amount of Halon 1301 required to extinguish Tefzel cable fires should be base'd on surface burning
~~
fires in accordance with NFPA 12A~, i.e. , 6. percent for 10 minutes.
Based on the burning characteristics..of Tefzel cable, fire test results in
non-Tefzel cables, anc NFPA for acceptance, for non-Tefzel cable we find
'that an automatic 'Halon 1301 extinguishing system with an adequate amount of Halon 1301 to achieve a 6 percent concentration'for a 10 minute' soak time will extingu'ish cable fires in PGCC's enclosures'which contain 80 percent Lor greater by weight Tefzel cabling, n
Conclusion -
Based on our evaluation, we conclude .that an automatic Halon 1301 extinguishing
, system with an adequate amount of Halon 1301 to achieve a 6 percent concentra-tion for a 10 minute soak time will be acceptable for PGCC's which contain
-80 peretnt or greater by weight Tefzel cabling. Therefore, we find General Electric's request for deviation from NED0-10466A acceptable.
.