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Category:PRELIMINARY SAFETY ANALYSIS REPORT & AMENDMENTS (PSAR
MONTHYEARML19309C5541967-05-0101 May 1967 App 2A to TMI-1 PSAR, Engineering Geology & Foundation Considerations. Includes Revisions 1-11 ML19309C5381967-05-0101 May 1967 Chapter 1 to TMI-1 PSAR, Introduction & Summary. Includes Revisions 1-11 ML19309C5391967-05-0101 May 1967 Chapter 2 to TMI-1 PSAR, Site & Environ. Includes Revisions 1-11 ML19309C5411967-05-0101 May 1967 Chapter 3 to TMI-1 PSAR, Reactor. Includes Revisions 1-11 ML19309C5421967-05-0101 May 1967 Chapter 4 to TMI-1 PSAR, Rcs. Includes Revisions 1-11 ML19309C5431967-05-0101 May 1967 Chapter 5 to TMI-1 PSAR, Containment Sys. Includes Revisions 1-11 ML19309C5441967-05-0101 May 1967 Chapter 7 to TMI-1 PSAR, Instrumentation & Control. Includes Revisions 1-11 ML19309C5451967-05-0101 May 1967 Chapter 8 to TMI-1 PSAR, Electrical Sys. Includes Revisions 1-11 ML19309C5461967-05-0101 May 1967 Chapter 9 to TMI-1 PSAR, Auxiliary & Emergency Sys. Includes Revisions 1-11 ML19309C5471967-05-0101 May 1967 Chapter 10 to TMI-1 PSAR, Steam & Power Conversion Sys. Includes Revisions 1-11 ML19309C5481967-05-0101 May 1967 Chapter 11 to TMI-1 PSAR, Radwastes & Radiation Protection. Includes Revisions 1-11 ML19309C5491967-05-0101 May 1967 Chapter 12 to TMI-1 PSAR, Conduct of Operations. Includes Revisions 1-11 ML19309C5501967-05-0101 May 1967 Chapter 13 to TMI-1 PSAR, Initial Tests & Operation. Includes Revisions 1-11 ML19309C5511967-05-0101 May 1967 Chapter 14 to TMI-1 PSAR, Safety Analysis. Includes Revisions 1-11 ML19309C5521967-05-0101 May 1967 Chapter 15 to TMI-1 PSAR, Tech Specs. Includes Revisions 1-11 ML19309C5531967-05-0101 May 1967 App 1A to TMI-1 PSAR, Technical Qualifications. Includes Revisions 1-11 ML19309C5711967-05-0101 May 1967 Suppl 4 to TMI-1 PSAR, Eccs. ML19309C5551967-05-0101 May 1967 App 2B to TMI-1 PSAR, Seismology & Meteorology. Includes Revisions 1-11 ML19309C5591967-05-0101 May 1967 App 2C to TMI-1 PSAR, Groundwater Hydrology. Includes Revisions 1-11 ML19309C5611967-05-0101 May 1967 App 5A to TMI-1 PSAR, Structural Design Bases. Includes Revisions 1-11 ML19309C5621967-05-0101 May 1967 App 5B to TMI-1 PSAR, Design Program for Reactor Bldg. Includes Revisions 1-11 ML19309C5631967-05-0101 May 1967 App 5C to TMI-1 PSAR, Design Criteria for Reactor Bldg. Includes Revisions 1-11 ML19309C5641967-05-0101 May 1967 App 5D to TMI-1 PSAR, Qc. Includes Revisions 1-11 ML19309C5651967-05-0101 May 1967 App 5E to TMI-1 PSAR, Liner Plate Spec. Includes Revisions 1-11 ML19309C5661967-05-0101 May 1967 App 5F to TMI-1 PSAR, Reactor Bldg Instrumentation. Includes Revisions 1-11 ML19309C5671967-05-0101 May 1967 Suppl 1 to TMI-1 PSAR, Answers to AEC Questions. ML19309C5691967-05-0101 May 1967 Suppl 2 to TMI-1 PSAR, Answers to AEC Questions. ML19309C5701967-05-0101 May 1967 Suppl 3 to TMI-1 PSAR, Answers to AEC Questions 13.0-18.7. ML19309C5571967-01-19019 January 1967 App 2B,Part 1,to TMI-1 PSAR, Seismicity & Response Spectra Analysis,Proposed Nuclear Power Plant,Tmi,Susquehanna River, Pa. Prepared for Gilbert Associates,Inc ML19309C5601967-01-14014 January 1967 App 2D to TMI-1 PSAR, Geologic Investigation of TMI & Vicinity. Prepared for Gilbert Associates,Inc ML19309C5581963-12-31031 December 1963 App 2B,Part 2,to TMI-1 PSAR, Meteorology. 1967-05-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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APPEICIX 5A STRUCTURAL DESIGH 3ASES O
v AEC Publication TD-7024, " Nuclear Reactors and Earthquake," as a=plified herein vill be used as the basic design for seismic analysis.
Structural design for nor=al operating conditions vill be governed by the applic".ble design codes. The design for the loss-of-coolant accident and
=axist f.s=ic condition vill ensure no loss of functions when related to public safety.
1 CLASSES OF STRUCTURES AND SYSTIM The plant structures, cc=ponents, and syste=s will be classified according to their function and the degree of integrity required to protect the public.
The classes are:
1.1 CLASS I These structures, cc=ponents, and systems, including instruments and centrols, whose failure =ight cause or increase the severity of a loss-of-coolant acci-dent or result in an uncontrolled release of excessive escunts of radicactivit-and those structures and ec=penents which are vital to safe shutdown and isolation of the reactor are classified Class I. W en a syste= as a whole is referred to as Class I, certain less essential portions not associated with less of function of the syste= =ay later be designated under Class II or III as appropriate. Examples of Class I structures, cc=ponents, and systems are:
O- a. Reactor Building and its penetrations including plant. vent.
- b. Reactor Building crane.
- c. Reactor vessel and its internals including control rod drive assemblies.
- d. Vital ecoling water systems.
- e. Pri=ary system including vents and drains within Reactor Building.
- f. Spent fuel ecoliag syste= and shutdevn cooling system.
- g. Makeup and purification system.
- h. En61neered safeguards systems including their electrical power scurces and distribution systems.
- i. Fuel stcrage pool.
n V
l 3,_1 0002 TSS l
l l
J. Reactor control rocs and equipment.
- k. Waste disposal syste=.
- 1. Post-incident filtration syste=.
1.2 C1 ASS I!
Those structures, cc=ponents, and systems which are i=portant to reactor operation but not essential to safe shutdown and isolation of the reactor and whose failure could not result in the release of substantial a=ounts of radioactivity are classified Class II. Examples of Class II structures, components, and systems are:
- a. Secondary coolant system.
- b. Electric power system, except emergency syste=s.
- c. Auxiliary building, and waste disposal building, except as included in Class I above.
1.3 CLASS III Those structures, co=ponents, and systems which are not related to reactor operation or containment are classified Class III.
2 CLASS I DESIGN 3ASES All structures, components, and systems classified as Class I vill be desi6ned in accordance with the following criteria:
- a. Primary steady state stresses, when ecmbined with the seismic stress resulting from the response to a ground acceleration of 0.C6 6 acting horizontally and 0.0h g acting vertically and occurring simultaneously shall be maintained within the allowable working stress limits accepted as good practice and, where applicable, set forth in the appropriate design standards, e.g., ASME Boiler and Pressure Vessel Code, ASA 331.1 Code for Pressure Piping, Building Code Requirements for Reinforced Concrete, ACI 318 and AISC Specifications for the Design and Erection of Structural Steel for Buildings.
- b. Pri=ary steady state stress when ecmbined with the seismic stress resulting from the response to a ground acceleration of 0.12 g acting horizontally and 0.08 g acting vertically and occurring 2 simultaneously, shall be li=1ted so that the function of the co=-
ponent, system, or structure shall not be impaired as to prevent a safe and orderly shutdown of the plant.
O
,., t ,)
. i 5A-2 (Revised 10-2-67)
3 CLASS II DESIGN BASES O All structures, components , and systems classified as Class II vill be designet for a ground acceleration of 0.06 g in accordance with procedures of the Unife Building Code.
k CLASS III DESIGH BASES All structures , ccuponents , and systems classified as Class III vill be designe in accordance with applicable building code requirements.
5 DAMPING FACTORS The folleving gives the damping factors used in the seismic design of component and structures.
Per Cent of Ccnconent 02 Structure Critical Damuing
- 1. Reactor Building 2.0
- 2. Concrete Support structures inside the Reactor Building 2.0
- 3. Assemblies and Structures a) Bolted or Riveted 2.5 b) Welded 1.0
- h. Vital Piping Systens 0.5 5 Other Concrete Structures above ground 5.0 6 METHOD OF ANALYSIS The acceleration response spectra included in Appendix 23 vill be used for the design of Class I and II structures , ccuponents , and systems. The vertica' cc=ponent of ground motion is assumed to be 2/3 of the horizontal ccuponent.
The vertical and horizontal components are assumed to occur simultaneously anc their effects added algebraically.
For Class I structures, ecmponents , and systems the method of enalysis will either be a =odal analysis wherein modal shapes , frequencies , stresses , and proportionality factors are detemined or vill be perfomed as follows:
- a. The natural period of vibration of the structure, ccaponent, or syste vill be detemined.
- b. The response acceleration of the ecmponent to the seismic motion vil:
be taken frcm the response spectrum curve at the appropriate natural period, h4 ,
0002 357 5A-3
- c. Stresses and deflections resulting from the ecmbined influence of normal loads and the additional load frcm the 0.06 g earthquake vill te calculeted and checked aEainst the limits i= posed by the design standard or code.
- d. Stresses and deflections resulting frem the ccebined influence of the normal loads and the additional loads frem the 0.12 6 earthquake vill be calculated and checked to verify that deflections do not preveni.
functioning and that stresses do not produce rupture or excessive distortion.
- e. The dynamic analysis of critical piping systems (i.e. . Class I systems )
vill'be a modal analysis based upon either a distributed or lumted-mass solution depending upon the complexity of the system. The two arproacnes are performed as follows :
- 1. Distributed-Mass Analysis
[
L The system is renresented by a number of straight uniform beams with a distributed mass and stiffness. First, the transfer matrix for each of the straight beams is deter =ined and the rotation trans-fer matrix for each . joint calculated. Next the enuation of motion
{ is written in matrix form. Previously determined transfer matrices l are used. Considering the acpropriate boundary conditions. the
characteristic determinant is generated. When the natural frequen-cies are known. the corresponding mode shapes are determined. Then.
l by using the response spectrum for a single-degree-of-freedom system, the maximum displacements are obtained as the root-mean-square sum of the modal maxim a. Finally, after the maximum displac ments are kncvn, forces and moments are calculated at the structural
.ioints.
- 2. Lumped-Mass Analysis The system is represented by a series of cencentrated masses. First the scace coordinates are established for the system and enordinates are established for the system and coordinates of = ass coints are determined. Using a static analysis, flexibility matrices corres-ponding to these mass points are commuted. Next, the ecuations of i
motion isare method written in matrix form. Force influence coefficients used.
assuming harmonic Natural motionfrecuencies and mode shaces are obtained of the system.
i Finally, using -he same tee
! nique as for the distributed-mass analysis, maximum internal forces and moments are calculated at the structural joints.
In additien to the earthquake response for the pipe system, the moda described above vill be used to determine forces and moments with resulting stresses for any transient or termanent displacements whic vill be induced at the suprort peints.
T RIFERESCES a., Nuclear Feactors and Earthauakes. AEC Publication TID ~iO24 0002 358 9 b.
Wind No. 3269.Forces on Structures. Task Cocm:ittee on vind fems. ASCE Pacer ~
..- 5A k (Bevised 1-8-68)