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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20135A2961996-02-29029 February 1996 Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept ML20058A4121993-08-31031 August 1993 Rev 1 to Suppl 4 to CENPD-279, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20073H8181991-03-30030 March 1991 WCAP-12920, Analysis of Southern California Edison Co San Onofre Unit 3 Reactor Vessel Surveillance Capsule Removed from 97 F Location ML20062G8021990-11-30030 November 1990 Applicability of Notrump to San Onofre Nuclear Generating Station Unit 1 ML20055H2451990-06-25025 June 1990 Overheads/Passouts from NRC Review of San Onofre Nuclear Generating Station 1 Thermal Shield Design Analysis ML19324C4241989-10-31031 October 1989 Rev 0 to San Onofre Units 2 & 3 Fuel Rack Seismic Analysis for Final Pool Layout. ML20073K6781989-06-30030 June 1989 Risk Evalution of Removal of Shutdown Cooling Sys Autoclosure Interlock, Prepared for C-E Owners Group ML20235K9371989-02-28028 February 1989 Engineering Evaluation of San Onofre Nuclear Generating Station I Thermal Shield Supports ML20235Z0931989-02-28028 February 1989 Fuel Rack Seismic Analysis Methods & Parameters ML20154A6351988-07-31031 July 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20205Q4601986-05-31031 May 1986 Nonproprietary SONGS 2 End of Cycle 2 Shoulder Gap Evaluation ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20151Z0521986-01-31031 January 1986 Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure ML20151Z0641986-01-31031 January 1986 Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines ML20154L6991985-12-31031 December 1985 Spray Additive Tank Deletion Analysis for San Onofre Nuclear Generating Station Units 2 & 3 ML20134M7891985-08-31031 August 1985 Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program ML20134N3021985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Core Protection Calculator ML20134N2941985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Control Element Assembly Calculator ML20126H8321985-04-30030 April 1985 Nonproprietary Core Protection Calculator Improvement Program:Detailed Presentation to Nrc ML20112K0551985-03-31031 March 1985 Evaluation of Steam Generator Tube & Diagonal Spacer Strip Interaction & Wear,San Onofre Unit 2 ML20114C3771985-01-31031 January 1985 Nonproprietary End of Cycle 1 Shoulder Gap Evaluation ML20114B8211985-01-31031 January 1985 Nonproprietary Addendum to CEN-291(S) Response to NRC Questions on San Onofre Nuclear Generating Station Units 2 & 3,Cycle 2 ML20214E4801984-11-30030 November 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - San Onofre Nuclear Generating Station Unit 1, Technical Evaluation Rept ML20099C2851984-11-30030 November 1984 Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Software Mods ML20204H4281984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Ii,Uncertainty Analysis of Limiting Safety Sys Settings ML20099C2321984-10-31031 October 1984 Nonproprietary Rev 1 to San Onofre Nuclear Generating Station Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing ML20204H4971984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Iii,Uncertainty Analysis of Limiting Conditions for Operation ML20093N2661984-07-31031 July 1984 Nonproprietary Cpc/Ceac Software Mods for San Onofre Nuclear Generating Station Units 2 & 3. Info Deleted ML20093N2501984-06-30030 June 1984 Nonproprietary Safety Analysis & CPC Methodology Changes for San Onofre Nuclear Generating Station,Units 2 & 3. Info Deleted ML20095F9411984-03-31031 March 1984 Nonproprietary Version of Rev 0 to SONGS-2 Cycle 1,CPC & Ceac Data Base ML20080K3231983-09-30030 September 1983 Suppl 1,Rev 1,to PRA of Effects of PORVs on Depressurization & Dhr ML20072J5071983-06-30030 June 1983 Depressurization & Dhr,Responses to NRC Questions ML20072J5371983-06-30030 June 1983 Suppl 1 to CEN-239, PRA of Effects of PORVs on Depressurization & Dhr,San Onofre Nuclear Generating Station,Units 2 & 3 ML20070M1291983-01-31031 January 1983 Natural Circulation Test Program,San Onofre Nuclear Generating Station,Unit 2,Natural Circulation Cooldown ML20052B6411982-03-31031 March 1982 Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss.Prepared for C-E Owners Group. ML20039F8601981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels. ML20010F2971981-09-0303 September 1981 Errata Pages to CEN-160-(S)-P, CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station, Units 2 & 3. Formal Submittal Will Be Provided ML20010C7781981-08-0505 August 1981 Nonproprietary Version of San Onofre Nuclear Generating Station 2,Cycle 1,CPC & Ceac Data Base Document. ML20010A2931981-07-31031 July 1981 to Comprehensive Vibration Assessment Program Final Rept. ML20126L3571981-05-31031 May 1981 Nonproprietary Version of, Responses to NRC Concerns on Applicability of CE-1 Correlation to SONGS Fuel Design ML20004D8231981-05-31031 May 1981 Nonproprietary Version of CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station,Units 2 & 3. ML20010C7701981-03-31031 March 1981 Nonproprietary Functional Design Spec for Core Protection Calculator,Response to NRC Questions 221.18 & 221.20. ML20010C7721981-03-31031 March 1981 Nonproprietary, Functional Design Spec for Control Element Assembly Calculator,Response to NRC Questions 221.18 & 221.20. ML13312A5661980-06-30030 June 1980 Response to NRC Question 222.34, Nonproprietary Version, June 1980 ML20010H7041979-11-15015 November 1979 Plant Protection Sys Selection of Trip Setpoint Valves, Revision 00 1998-07-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20195H2471998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Songs,Units 2 & 3 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20154M7921998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Songs,Units 2 & 3 ML20155F6081998-09-17017 September 1998 Non-proprietary Version of San Onofre 2 & 3 Replacement LP Rotors ML20151Z9851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Songs,Units 2 & 3 ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20237B8571998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Songs,Units 2 & 3 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20236R1031998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Songs,Units 2 & 3 ML20249A9431998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Songs,Units 2 & 3 ML20248B8981998-05-26026 May 1998 Updated SG Run Time Analysis Cycle 9 ML20248B9221998-04-30030 April 1998 Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9 ML20247L5181998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Songs,Units 2 & 3 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)1998-04-0606 April 1998 LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) ML20217Q6161998-04-0505 April 1998 Failure Analysis Rept 98-005,Failure Analysis of 2HV9305 Motor Starter ML20217A0141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Songs,Units 2 & 3 ML20217D4701998-03-0202 March 1998 Rev 1 to 90459, Failure Modes & Effects Analysis DG Cross- Tie,DCP7048.00SE ML20216J3551998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Songs,Units 2 & 3 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20203K9141998-02-0303 February 1998 Rev 0 to ESFAS Radiation Monitor Single Failure Analysis. W/96 Foldout Drawings ML20202F9731998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Songs,Units 2 & 3 1999-09-30
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SAN ONOFRE UNITS 2 AND 3 DOCKETS 50-361 AND 50-362 CEN-127(S) - NP RESPONSE TO NRC QUESTION 222.34 NON-PROPRIETARY VERSION JUNE, 1980 COMBUSTION ENGINEERING, INC.
NUCLEAR POWER SYSTEMS POWER SYSTEMS GROUP WINDSOR, CONNECTICUT 06095 8c08220
LEGAL NOTICE This response was prepared as an account of work sponsored by Conibustion Engineering, Inc. Neither Combustion Engineering nor any person action on its behalf:
- a. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this response, or that the use of any information, apparatus, method or process dis closed in this response may.not infringe privately owned rights; or
- b. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this response.
CRITERIA FOR PROPRIETARY INFORMATION Information contained in this report which is delimited by means of surrounding brackets is proprietary to Combustion Engineering, Inc. Code numbers 1-6 have been placed in the vicinity of such brackets to classify this proprietary information. The following list identifies the classification criteria associated with these code numbers.
Code Criteria 1 The information reveals privileged cost or price information, commercial strategies, production capabilities, or budget levels of Combustion Engineering, Inc., its customers or suppliers.
- 2. The information reveals data or material concerning Combustion Engineering or customer funded research or development plans or programs of substantial present or potential competitive advantage to Combustion Engineering, Inc.
3 The use of the'information by a competitor would substantially decrease his expenditures, in time or resources, in designing, producing or marketing a similar product.
4 The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering, Inc.
5 The information reveals special aspects of a process, method, component or the like, the exclusive use of which results in a substantial competitive advantage to Combustion Engineering, Inc.
6 The information contains ideas for which patent protection is likely to be sought..
Question 222.34 The results of the submitted answer to the staff questions (Amendment 16 September 1979) are surprising. Therefore, we would like to verify some of the results by performing in-house audit calculations. To expedite our audit calculations, provide the input data (actual input used in the CESEC and TORC codes) for the following cases:
Steam line break with offsite power from full power.
Steam line break without offsite power from full power.
Steam line break without offsite power from hot zero power.
Worst feedline break case.
Response is a description of input data to the CESEC code, which was used in the steam line break analysis. Attachment 2 describes additional input data required for the CESEC-ATWS code, which was used in the feedwater line break analysis. The following information is provided for each input:
- 1. The input variable vector location;
- 2. The alphanumeric designation of the input variable;
- 3. The engineering units of the input variable, and
- 4. A brief description of the input variable.
Attachments 3 through 6 provide the numerical CESEC (or CESEC-ATWS) input data for the full power steam line breaks with and without offsite power available, the hot zero power steam line break without offsite power available, and the worst feedwater line break, respectively.
Input vector locations defined in Attachments 1 and 2 for which no numerical values are given in one or more of the Attachments 3 through 6 assume the value zero. Data on lines identified with an asterisk (*)
do not affect the results of the particular transient. They are provided either as suggested time step or edit control options, or because CESEC requires a non-zero value for certain input variables for its initializa tion calculations even though they are not used in the transient calculations. The format of the input data as read by CESEC is (AlO,4X, Il, 15,6F10. 0). is a complete numerical CESEC input listing for the full power steam line break with offsite power available, failure of one high pressure safety injection (HPSI) pump, and stuck control element assembly (CEA). Attachments 4 and 5 list, for the full power steam line break without offsite power available and for the hot zero power steam line break without offsite power available (both with failure of one HPSI pump and stuck CEA), respectively, those input variables whose values differ from the values specified in Attachment 3.
As discussed in paragraph 15.2.3.1.3.1 of the FSAR, the feedwater line break was analyzed using the CESEC-ATWS code, with modifications for incorporating the Henry-Fauske correlation into the feedwater line break model, for controlling rampdown of the effective steam generator heat
-2 transfer area, and for automatically changing the disposition of systems affected by the loss of offsite power. A complete CESEC-ATWS input listing for the worst case feedwater line break (0.2ft 2 break, instan taneous rampdown of heat transfer area, failure of one auxiliary .
feedwater pump, stuck CEA, loss of offsite power) is given in Attachment 6.
A description of the input data to the TORC code is given in Appendix B of CENPD-161. The numerical TOPC input listing for the full power steam line breaks.-is given in Attachment 7. Card 2 of card group 11, the input location for transient operation conditions, contains values for nominal full power conditions. Transient values for these variables are obtained from CESEC output.
ATTACHMENT 1 Description of CESEC Inputs (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
- C ATTACHMENT 2 Description of CESEC-ATWS Inputs Not Listed in Attachment 1 (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
ATTACHM1ENT 3 CESEC Input Listing for the Full Power Steam Line Break Inside Containment With Offsite Power Available, Failure of One High Pressure Safety Injection Pump, and Stuck Control Element Assembly (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
ATTACHMENT 4 CESEC Input Listing for the Full Power Steam Line Break Inside Containment Without Offsite Power Available, Failure of One High Pressure Safety Injection Pump, and Stuck Control Element Assembly (only that data which is different from the data in Attachment 3 is listed)
(The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
ATTACHMENT 5 CESEC Input Listing for the Hot Zero Power Steam Line Break Outside Containment Without Offsite Power Available,Control Failure of One High Pressure Safety Injection Pump, and Stuck Element Assembly in Attachment 3 is (only that data which is different from the data listed)
(The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
ATTACHMENT 6 CESEC-ATWS Input Listing for the Worst Case Feedwater Line Break ith Loss of Offsite Power, Failure of One Auxiliary Feedwater Pump, and Stuck Control Element Assemblv (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
ATTACHMENT 7 TORC Input Listing for Full Power Steam Line Break (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)
PAPRIETARY INFORMA11N NOTICE THE ATTACHED DOCUMENT CONTAINS "PROPRI ETARY INFORMATION" AND SHOULD BE HANDLED AS NRC "OFFICIAL USE ONLY" INFORMATION. IT SHOULD NOT BE DISCUSSED OR MADE AVAILABLE TO ANY PERSON NOT REQUIRING SUCH INFORMA TION IN THE CONDUCT OF OFFICIAL BUSINESS AND SHOULD BE STORED, TRANSFERRED, AND DISPOSED OF BY EACH RECIPIENT IN A MANNER WHICH WILL ASSURE THAT ITS CONTENTS ARE NOT MADE AVAILABLE TO-UNAUTHORIZED PERSONS.
COPY NO.
DOCKET NO.
CONTROL NO.
REPORT NO.
REC'D W/LTR DTD.
NRC Form 190 (4-78)
PROPRIETARY INFORMATION