|
---|
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
MONTHYEARML20217G1001999-10-14014 October 1999 Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.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 ML20211E8731999-08-24024 August 1999 Safety Evaluation Supporting Amend 215 to License DPR-50 ML20211B1931999-08-19019 August 1999 Safety Evaluation Supporting Amend 214 to License DPR-50 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 05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
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 ML20212H9101999-06-21021 June 1999 Safety Evaluation Supporting Amend 212 to License DPR-50 05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With
ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With 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 05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
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 ML20205Q6111999-04-15015 April 1999 Safety Evaluation Supporting Amend 210 to License DPR-50 ML20205Q5981999-04-13013 April 1999 Safety Evaluation Supporting Amend 209 to License DPR-50 ML20206P2841999-04-12012 April 1999 SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90 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) 05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.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 05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
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 05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 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 05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
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 05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With 05000289/LER-1998-011, :on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge1998-09-23023 September 1998
- on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge
05000289/LER-1998-009-01, :on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised1998-09-18018 September 1998
- on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised
1999-09-30
[Table view] |
Text
APPENDIX 2C GROUND-WATER HYEROLOGY 1 INTRODUCTION 1.1 GENERAL Three Mile Island Nuclear Station vill be -located on a large island in the Susquehanna River. Purely frem the standpoint of geography, its ground-water conditions are unique, but relatively constant, and predictably controlled by the Susquehanna River, itself. The drainage area of the Susquehanna River extends frem its source at Otsego Lake, Cooperstown, New York, for a distance of 4hh miles , across the States of Pennsylvania and Maryland, and teminates in the Chesapeake Bay. This major water cour:e collects all surface runoff and ground-5 ater seeps as well as their respective centaminants frm a water-shed of e,,,roximately a 27,000 square mile area. Three Mile Island is located about midway along the course of the river and therefore is influenced by the quantity and quality of that portion of the water frem the Susquehanna River watershed upstream frm the island. Average annual rainfall at the site is h0 inches.
1.2 MODE OF OCCURRENCE The bedrock underlying the general area is ccmposed of shales , sandstones ,
and siltstones belonging to the Gettysburg shale of Triassic Age. A vide range in yields occurs within the romation, with the sandstone facies nomally being the best aquifers. Ecvever, in closely jointed or fractured O shales , relatively high yields can occur. The alluvial J.eposits are not believed to be a major source of ground-water in this area.
2 SITE STUDIES Ground-vater was studied at the site by means of:
- a. Stand pipes to record elevation and fluctuation of water levels
- b. A pu= ping out test to detemine permeability of Se saturated soil
- c. A falling head pemeability test to determine pemeability of soil above the water table Ground-water at the proposed station site occurs under water table conditions.
The water table reaches its maximum elevation at the highest topegraphic point in the center of the island and falls off tcvard both the east and vest shores. A variation of only about 5 ft occurs frem either side to the center producing a gradient of approxi=ately 0.6 per cent tcvard the river.
At twenty observation points in and surrounding the plant area, water levels occurred generally at a depth in excess of 15 ft and ranged from lh to 19 ft.
The ground-vater level occurred at a =aximum of 6.2 ft above the top of rock with less than 1 ft of head existing above the soil-rock interface at one q point of observation.
m *7 b 8004080 //
e.s
'w
. n ... . .. . .
0002 313 2C-1 L
1 The water level of the Susquehanna River controls Three Mile Island ground-water levels. A rapid rise in the river in response to a heavy rain and thaving of ice jams during Januar/,1967 was seen to produce significant rises in the water levels of observation vells 200 feet frcm the water's edge. Since a positive head exists on the island, any =ovement of ground- l vater frca the plant site vould be tcvard either channel of the river, and vould eventually enter the stream. The river would act as a r.atural boundarf, li=iting the dispersal of grenad-water frcm the island to the river. Teo facters are important in considering the possibility of infiltratica of ,
ground-water into the underlying Gettysburg shale and transmission to en j shore water supplies:
l
- a. A maxi =um positive head of 6 feet exists above the impervious (relativ to the soils ) Gettysburg for=ation.
- b. Ground-water levels are higher on either shore of the river, with hydraulic gradients sloping tcvard the River.
In order fer ground-water to move frem Three Mile Island to the mainland, it would be necessary to reverse the hydraulic gradient on the =ainland, which would necessitate partial devatering of the Susquehanna River.
Further, it is unlikely that river water vould ever significantly infiltrate rocks en either shore, except under sustained high capacity pumping, creating induced infiltration. A natural condition of river water flowing into the ground would not be nomal to this climate and geography.
The length of time required for the ground-water to move to the river is problematical. Teo types of tests have been run to date, in an attempt to establish pemeability of the soils overlying the bedrock. A pumping out test was run on the eastern side of the island and the results detemined indicated the pemeability of the saturated soil zone to be on the order of 10-2 c=/sec. A falling head test was run in the center of the island to detemine the gemeability of unsaturated soil. This test produced a co-efficient of approxi=ately 10-J cm/s ec. These results confi m ed these gemeabilities estimated frca examining the centinuous samples frcm the test borings. Scme change in slope of the water table vill occur due to the varia-tions of the river level and temporary minor reversal of ground-water movement vill prebably result during pericds of high water or during periods of extended drought. Any additional impoundment of water in either channel vould necessaril; have an effect en the direction of ground-water movement and on the sicpe of the water table but in any event the final discharge point vould still be into the river.
1 l 3 AREA WATER WELL DATA l
l Most of the available data on ground-water vells in the Gettysburg shale, at this time, ca::es directly frem the U. S. Geologic Survey water supply paper en the ground-water resources of Olmsted Air Force Base at Middletevn. The base is located apprcximately two and one-half miles north of Three Mile Island.
O
- ?
- '. ~ 0002 314 2C-2 -
s The average strike of the femation in this area is N h3 with dips at angles varying fica 19 to 38 degrees. The rock consists of alternating layers of fine to coarse-grained sandstone, siltstece, and shale.
Ground-vater occurs under artesian conditions at the base. In 20 vells rangin6 frm 300 to 800 feet in depth, specific capacities of the aquifers tapped ranged fra 0.33 to 15.0 and transmissibilities varied frem 1,200 gpd per ft to scmewhat less than 50,000 gpd per ft. The pH of wells tested were frem 6.6 to 8.1, hardness fra 137 to 826 ppn and dissolved solids frem 200 to 1,340 ppn. In Hall's " Ground-vater in Southeastern Pennsylvania", the Brunswick shale (the name applied to the eastern counterpart of the Gettysburg) and the Gettysbu shale were cmbined and included tcgether in tabulations. Of 112 vells surveyed the depths ranged from 18 to 500 feet, with an average depth of 157 feet. Yield ranged frca 0-200 gallons per minute with an average yield of 41. Six analyses were included showing the range of total dissolved solids to be between 201 and 786 ppm, hardness frm 152 to h99 ppm and iron frem 0 5 to h.9 ppm. Since these are fairly deep rock aquifer wells where water chemistry is a function of miner-alogy of the reservoir rocks , one should not expect the alluvial ground-water to be of similar chemical makeup.
O O
0002 4 5 2C-3
--