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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20210P4461997-08-31031 August 1997 Update 2 to TMI-2 Post-Defueling Monitored Storage Sar ML20210T3411997-08-31031 August 1997 Rev 0 to TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20199E5841997-08-18018 August 1997 Limited Liability Company Agreement of Amergen Energy Co, LLC Among PECO Energy Co,British Energy PLC & British Energy,Inc ML20133D8771996-12-23023 December 1996 Rev 2 to TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20137F1301996-08-27027 August 1996 Rev 0 to Auxiliary Bldg Sump Sludge Prevention (Regulatory Required) ML20117H6621996-07-20020 July 1996 Rev 1 to TR 094 TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20129G9291996-06-17017 June 1996 TMI-1 Reload Design & Setpoint Methodology ML20148F0831996-04-0202 April 1996 Rev 0 to EDG 1B Air Start 2 Reservoir Tank ML20148F0611996-04-0202 April 1996 Rev 0 to SQ-TI-EG-T-0001B-1, EDG 1B Air Start 1 Reservior ML20098B1291995-09-19019 September 1995 Rev 1 to Pages 3 & 30 of TMI-1 USI A-46 Seismic Evaluation Rept ML20100L6581995-05-25025 May 1995 Div 1/2 Mod Design Description for New TMI-1 Radwaste Demineralizer Sys Three Mile Island Unit 1,Nuclear Generating Station, Rev 2 ML20087J5281995-05-11011 May 1995 Nonproprietary Page 2 of TMI Unit 1 USI A-46 Seismic Evaluation Rept ML20082G4191995-03-22022 March 1995 Rev 0 to Topical Rept 093, TMI-1 Reactor Bldg Twenty Yr Tendon Surveillance (Insp Period 6) ML20082Q8051995-03-10010 March 1995 TMI-1 Core Thermal-Hydraulic Methodology Using VIPRE-01 Computer Code ML20082G4441995-02-22022 February 1995 Vols I & II 20th Yr Physical Surveillance of TMI-1 Containment Bldg ML20100L6321994-08-0303 August 1994 Shipment of Miscellaneous Waste Evaporator Concentrates ML20059M2181993-11-30030 November 1993 Amend 19 to Pdms Sar ML20148F1011993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16B ML20148F0931993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16A ML20059F0471993-08-31031 August 1993 Amend 18 to Post-Defueling Monitored Storage (Pdms) Sar. W/Rev 2 to List of Pdms Requirements & Commitments ML20056E5921993-07-31031 July 1993 Conservative Design In-Structure Response Spectra for Resolution of USI A-46 for Tmi,Unit 1 ML20059D7351993-02-0707 February 1993 Review of Offsite Response to Site Area Emergency Incident at Three Mile Island Nuclear Station ML20126D2831992-12-18018 December 1992 Criticality SAR for TMI-2 Reactor Vessel ML20114B9631992-08-0808 August 1992 Rev 3 to Criticality Safety Evaluation of TMI Fuel Storage Facilities W/Fuel of 5% Enrichment ML20058F6561992-07-31031 July 1992 Companion Sample Exams ML20058F6481992-01-31031 January 1992 Metallographic & Hardness Exams of TMI-2 Lower Pressure Vessel Head Samples ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20066K3591991-01-31031 January 1991 Rev 0 to Rept on 1990 Eddy Current Exams of TMI-1 OTSG Tubing ML20216K1251990-10-31031 October 1990 Amend 9 to Post-Defueling Monitored Storage Sar ML20217A4251990-09-11011 September 1990 Rev 3 to Licensing Rept for Spent Fuel Pool Mod of Pool a: TMI Unit I ML20058M7251990-08-0101 August 1990 Rev 2 to Div Technical Evaluation Rept for Processed Water Disposal Sys ML20056A0091990-07-26026 July 1990 TMI-1 Trust Agreements ML20043A2341990-05-0202 May 1990 Rev 0 to TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5). ML20055C9461990-03-31031 March 1990 Final Rept, TMI - Unit 2 Safety Advisory Board, for Mar 1981 - Dec 1989 ML20247R6371989-09-12012 September 1989 Submerged Demineralizer Sys ML20246H9401989-08-25025 August 1989 Corrected Pages 5-10 Through 5-18 & 5-26 to Rev 1 to Defueling Completion Rept,Second Submittal ML20246E1021989-08-18018 August 1989 Portion of Rev 1 to, Defueling Completion Rept ML20246G1161989-08-15015 August 1989 Rev 0 to SER for Removal of Metallurgical Samples from TMI-2 Reactor Vessel, Safety Analysis ML20247J2251989-07-31031 July 1989 Rev 7 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) ML20246E3481989-07-0505 July 1989 Rev 0 to TMI-2 Defueling Completion Rept ML20245K0151989-06-30030 June 1989 Amend 4 to Post-Defueling Monitored Storage Sar ML20246P8081989-05-31031 May 1989 Rev 12 to Defueling Water Cleanup Sys ML20244E3241989-04-30030 April 1989 Rev 7 to Technical Evaluation Rept 15737-2-G03-107, Waste Handling & Packaging Facility ML20235G5761989-02-0101 February 1989 Rev 0 to Criticality Safety Evaluation for Increasing TMI-2 Safe Fuel Mass Limit 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 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 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 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 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 ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) 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 ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With 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 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with 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 ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively 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 1999-09-30
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INTERIM REPORT ON FUEL DENSIFICATIO'!
FOR THE METROPOLITAN EDISON THREE MILE ISLAND NUCLEAR STATION UNIT 1 r
APRIL 1973 1584 303 2495 4911070SPf
- 1. INTRODUCTIO" At the presen t time , the Regulatory Staf f is evaluating topical reports BAW-10055, " Fuel Densification Report", and LAN-1388, " Fuel Densification Report for Oconee Uni t 1". It is enticipated that by May 1,1973, the evaluation will be comoleted of the applicaticn of E6W analytical models in accordance with the guidelines set forth in the " Technical Report on Densificaticn of Light Water Reactor Fuels", USAEC, of Novetber 14, 1972.
The purpose of this interim report is to: (1) provide the Staff with suf ficient information to compare Three Mile Island - Unit 1 (TMI-1) with Oconee 1 and to describe any changes in methods or application thereof in the final report for TMI-1, and (2) present c preliminary eva'.uation of the rated power capability of TMI-l even considcring fuel densification effects.
1584 04
- 2. S U'.'PAPli Based on the analysis performed for TMI-1 using the methods outlined in BAW-10055, including a change in the power spike model and a change in input to this model (see Section 3), the follcwing conclusions are nade assuming that the fuel pellets densify up to 96.5!! theoretical density.
- 1. C1cdding collapse will not occur prior to 21,000 effective full pcuer hours of operation (greater than one fuel cycle) .
- 2. The mechanical performance of B&W fuel rods will not be impaired.
- 3. The interim acceptance criteria for ECCS are =ct.
- 4. The reactor can be safely operated at a power level of 2535 Ifit with minor codifications to the reactor protection system se tpoints.
- a. A reduction in the overpower trip se tpoint from 114 to 112T; of 2335 MWt.
- b. A reduction in allowable imbalance limits.
- 5. The increase in power peaking from gaps in fuel rods due to the assured densification can be compensated for by base load cperation as cpposed to load.follouing.
e 1584 305
- 3. RESULTS 3.1 Power Spike Model The power spike model described in DA'J-10055 will be used as described, except for one minor modification to the model and one change to input as described in the following subcecticns which are revised versict.s of the same subsections in B!.W-10055. .
2.3.4. Calculations of the Marimum Veid Size in A::ial Interval The equation for the determination oS,the ma:;:inun gap size asha function of ar.ial positica has been nodified fron AL = 0.965 - Di + 2r( ) + 0.004 L(2) 2 _
to the following at = 0.965 - ci + 0.004 L(z) 2 The term c(z) has been elininated from the determination of =aximu=
axial gap as a result of discussions with the s taf f and their evaluation of the Point Beach 2 Nuclear Plant Analysis.
2.4.1 Pcwer Soikes Due to a Sincie Gan and 2.4.2 Power Scikes Dee to Co-?laner Caos The calculaticnal cathods described in 3A.i-10055 will be changed to reflect the use of the DOT, Sn transport theory code in both X-?
and R-Z geometries. The power spike in the adjacent rods eill be obtained using EDT in X-Y gecnetry and the variation with gap lencth will be obtained T584 306 9
- 3. Result;, (centine:d) us in g R-Z ge or..e try . The ch an ge redefines the po er Ipike as the power increase in the adjacent pin rcther than that used in the third sentence in s ubs e c tion 2. 4.1. , "(i.e. , the percentage increase at the edge of the surrounding fuel region)". B&W has known that this definition of the power spihe due to a single gap was conservative and unrealistic and the true power increase in the adjacent pin has been determined. The results have been compared to those reported by Brookhaven National Laboratory in their Deccaber 1972 report, "Feaking Factors in Pressurized Water Reactors with Fuel Densification". The ins t figure in this report (un-numb e re d) ,
" Correction Factor F on Finite Gap Lengths", shows BNL results that are less than those values calculated by B&W for the same fuel enrichnent.
Therefore, the BOW method is conservative cenpared to the BNL method.
The DOT transports theory code in X-Y geotetry will also be used instead of the PDQ07 dif fusion theory code to determine the power spike in a center rod duc to more than one gap at the sane antal height in a surrounding array of fuel rods. The use of the trensport calculation provides a more accurate description of the physical system than does the diffusion theory calculation.
For the TMI-1 reactor these correction f actors will be calculated for the second zone fuel enriche.ent (2.75 w/o as-built), since this zone experiences the highest power peaking of the three fuel enrichnents in Core *l.
The preliminary data indicate that the power spike factor shoun in Figure 2-12 for theTMI-l reactor will be about 1.11 to 1.20 at 140 inches.
The f ollowing discussion en several additional sections of B.i%-10055 is presented to indicate the cancer in which the final analysis for TMI-l.
will be performed.
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i584 307
3.2 Thc rna l Annivs's .
The application of the power spike factor in the analysis of fuel tcrperatures and D::BP analysis will be that approved by the staff for B A'.'-10 05 5 . The as-built data for TAI-l will, of course, be used in the evaluation.
The preliminary evaluation has shoun that the DNBR less due to deacification frc= about 92.5 to 90.5% T.D. results in a power peaking rargin reduction of about 4 ta 5%.
The fuel reiting criterion will be abcut 21 kU/f t based en a taximum first cycle burnup of 20,800 Eld /ttU, uhich includes a 10,% uncertainty margin.
These effects will be compensated for by reducing of the overpcrar trip setpoint from 114 to 112% of 2535 E!t and changing the operational ,
philosophy f rom load following to base loaded cperation.
3.3 Nuclear Analvsis The channe in operation from load following to a base loaded philosophy will reduce pcwer peaks more than enouch to .cc=pcasate for the effects derivec in section 3.2. This change in operation will allev greater imbalance trip limi ts , for T:iI-l than for Ocence I in spite of the fact that the average density is 92.5% cocpared to 93.5% T.D. and the fuel enrichment censidered in the deternination of the power spike facter is 2.75 w/o compared to 2.15 w/o for Oconee I.
ow w . .3 3.4 Sa fe ty Analvsis e The ground rules and acceptance criteria adopted for the Oconee 1 report vill be achered to in the T!'I-l c cl: sis.
Mechenical An alvets 3.5 The applica ica of the 2. cl. m colle, se ,2ds.1 vill be the sa ue fci to o, a>.!;catica v. cm >_ar A tor ccone 1. . ae ca l- en 'm' till be !- tha an-u n ? ;
1584 308
j
.S lt e ch.m ical , ris, (coatinutd) data. T. e re f ore ' clad e 'iapse is not prodicted prior to 21,000 ef fective full pc.;c: hourc of operatien, 4
i l1 I
mil m 1584 309