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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML19351A4371989-11-30030 November 1989 Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual. ML20248D4071989-09-27027 September 1989 Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20245K1211989-08-0202 August 1989 Rev 4 to SD 3184-007, Div Sys Description for Solid Waste Staging Facility ML20244C2961989-06-30030 June 1989 Rev 1 to Sys Description SD 3510-013, Div Sys Description for Reactor Bldg Sump Recirculation Sys ML20246M7931989-03-0909 March 1989 Rev 11 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154C7191988-06-0303 June 1988 Rev 10 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154Q6771988-05-27027 May 1988 Recovery Operations Plan ML20236M1621987-11-0909 November 1987 Radiological Environ Monitoring Program for TMI-1 ML20236M4281987-10-19019 October 1987 Vols 1 & 2 of 1987 TMI Annual Exercise Scenario ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20238C6391987-08-21021 August 1987 Rev 2 to Design Criteria 3255-86-0004, TMI-2 Design Criteria for Pressurizer Defueling Sys. W/One Oversize Figure ML20236K9601987-07-24024 July 1987 Rev 3 to 3184-007, Solid Waste Staging Facility Sys Description ML20215M3261987-06-19019 June 1987 Rev 16 to Organization Plan ML20215H0301987-06-15015 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 2 to 6415-IMP-1300.06. Addl Assistance & Notification & Rev 1 to 6415-IMP-1300.16, Contaminated Injuries. Updated Table of Contents Encl ML20215M1291987-03-20020 March 1987 Corrected NCRP Commentary 4, Guidelines for Release of Waste - Water from Nuclear Facilities W/Special Ref to Public Health Significance of Proposed Release of Treated Waste Waters at Tmi ML20214S4481986-12-31031 December 1986 TMI-2 Cleanup Program,Post-Defueling Monitoring Storage ML20212N6711986-12-17017 December 1986 Rev 2 to Test Procedure SC-1302-323 Isolator - Fault Testing. Test Results Encl ML20212H7821986-10-10010 October 1986 Rev 7 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20206U7611986-09-26026 September 1986 Rev 1 to SD 3520-010, Div Sys Description for Processed Water Storage & Recycled Sys ML20205E7891986-08-0707 August 1986 Rev 0-03 to Corporate Procedure 1000-ADM-1291.01, Safety Review & Approval Procedure ML20211Q8251986-06-0202 June 1986 Rev 4 to SDD-TI-614, Div I Sys Design Description for TMI-1 Remote Shutdown Sys ML20203N1761986-04-29029 April 1986 Rev 4 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) 1999-08-12
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FOR USE IN UNIT l ONLY e i;gn 1
- 04/14/82 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 E!ERGENCY PLAN IMPLEMENT'NG PROCEDURE POST ACCIDENT IN-PLANT SAMPLING , ,
Table of Effective Pages j Page Revision Page Revision Page Revision Page Revi sion 1.0 1 2.0 1 3.0 1 4.0 1 5.0 1 6.0 1 OoCC) t '
OJ f& J T2 Signature Date Signature Y~~lf'$5 Date U Document ID: 0007W
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t FOR USE IN UNIT l ONLY s#; S n1 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE POST ACCIDENT IN-PLANT SAMPLING 1.0 PURPOSE This procedure specifies the method of obtaining and analyzing prirrary coolant samples under accident conditions.
2.0 DISCUSSION A requirement exists for timely analysis of primary coolant under.emer-gency conditions without overexposure of personnel. Since radiation levels associated with sampling and analysis may be very high, special precautions are required. The Radiological Assessment Coordinator is responsible for implementing this procedure and to ensure that the sample I is obtained without incurring a radiation exposure to any individual in excess of 3 REM to the whole body and 18 3/4 REM to the extremities.
3.0 REFERENCES
None 4.0 EQUIPENT 4.1 Protective clothing 4.2 Self-contained breathing apparatus 4.3 Lead-glass shield 4.4 Remote handling tools 4.5 Leaded gloves 4.6 Source shield 4.7 Analytical equipment 4.8 Reagents 4.9 Glassware 1.0 FOR USE IN UNIT I ONLY i
FOR USE IN UNIT I ONLY 1004.15 Revision 1 4.10 Eberline Model 6112 Survey Meter (or equivalent) i 4.11 Wheeled cart 4.12 Lead bricks 5.0 INSTRUCTION 5.1 Prerequisites
- 1. The Nuclear Service Closed Cooling System is in operation per OP 1104-11.
- 2. The Instrument Air System is in operation per OP 1104-25.
- 3. The 480 volt supplies 1A ESV and 1B ESV are energized.
- 4. The DC Engineered Safeguards buses A and B are energized.
- 5. The Reclaimed Water Portion of the Nuclear Chemical Addition System is operational per OP 1104 47.
- 6. The Aux. Bldg. Sump has adequate capacity to receive water from the sample sink.
- 7. Hood Ventilation System in operation.
- 8. The original sample container shall be pre-labelled to specify time of sample, date of sample, sample location, sample type and the individual obtaining the sample. Subsequent dilution sample containers shall be pre-labelled to include dilution factor and original sample data.
- NOTE 1: All E S. Valves which are normally used in sampling :
- have controls in the sample room as well as on the :
- vertical E.S. panel. However, in order for a sample :
- room control to operate, the corresponding switch on :
- the E.S. panel must be in the " remote" position. :
- Call the Control Room before and after sampling. :
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FOR USE IN UNIT I ONLY 1004.15 Revision 1
- NOTE 2: Prior to sampling of R.C. Letdown or Pressurizer : i
- ensure that CA-V-110 and CA-V.16 are closed. Close :
- the sample hood. :
- NOTE 3: When making adjustments to CA-V-110, no personnel :
- will stand near the drain funnel in which relief :
- valve CA-RY-5 discharges. :
- NOTE 4: The Shift Super >isor must be notified prior to' :
- sampling. The RM-R6 recorder chart should be marked :
- accordingly. :
5.2 Precautions 5.2.1 Ensure that all required sampling equipment is available before initiating sampling.
5.2.2 Three technicians will be equipped as follows before any entrance to Sampling Room;
- a. Full protective clothing with double coveralls, booties, hood, cotton gloves and surgeons gloves and rainsuit.
- b. Self-contained breathing apparatus.
- c. Whole-body TLD, TLD finger ring for each hand, high range (0-5R) self-reading dosimeter for whole body and each wrist.
- NOTE: Should also use TLD wrist badge if available. :
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4 FOR USE IN UNIT I ONLY 1004.15 Revision 1 5.2.3 Personnel performing sampling will leave Sample Room and notify their Supervisor immediately if it appears that their quarterly exposure limit might be exceeded.
- NOTE: Monitor self-reading dosimetry frequently. :
5.3 Procedure
- NOTE: Ensure that CA.V-13, CA-V-1, CA-V-2 and CA-V-3 are :
- closed. :
5.3.1 Technician 1 will proceed as follows:
5.3.1.1 Don leaded gloves.
5.3.1.2 Enter Sampling Room carrying Teletektor with probe extended and perform rapid survey of radiation levels.
- NOTE: Radiation levels are expected to be relatively low :
- until sampling begins. :
5.3.1.3 Ensure that leaded glass shield in place in front of hood.
5.3.1.4 Ensure that wheeled cart with sample shield is in place at hood.
5.3.1.5 Place polyethylene sample bottle into hood with remote handling tool locked on.
5.3.1.6 Open C A-V 35, CA-V-33, CA-V 34, CA-V-25A, CA-V-268.
5.3.1.7 Close CA-V-26A, CA-V-25B , CA.V-26C, CA-V-25C, CA-V-110, CA-V 30, CA-V-31, CA-V-16.
5.3.1.8 Open CA-V-13, CA-V-2.
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FOR USE IN UNIT l ONLY g4;g,1 5.3.1.9 Slowly open CA-V-110 (flow restriction device) to obtain pressure of 40-60 PSIG on CA6 PI.
- CAUTION: Adjust CA-V-110 carefully since pressure of 125 PSIG : !
- downstream will cause CA to lift. :
...________.. _____________________ .___-RV-5 5.3.1.10 Return to step-off pad with Teletektor, check self-reading dosimeters and inform others of radiation levels encountered and exposure received.
- NOTE: Allow the sample to recirculate through the cooler :
- at least five minutes before proceeding. :
5.3.2 Technician 2 will proceed as follows:
5.3.2.1 Don leaded gloves.
5.3.2.2 Enter Sample Room with Teletektor extended and quickly check radiation level s.
5.3.2.3 Verify that temperature of 150* or less is indicated on CA4 TI.
5.3.2.4 Raise hood door, open CA-V-107 (demineralized water) and CA-V-16.
5.3.2.5 Lower hood to 100LFPM line.
- NOTE: Allow time to purge for approximately 15 seconds. :
- CAUTION: Check dosimeters while purging line. :
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FOR USE IN UNIT I ONLY g g,, i
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5.3.2.6 Obtain grab sample by placing bottle under drain line (hold sample bottle with remote handling tool).
- CAUTION: Obtain only 20-30 ML. in sample bottle (1-2 inch :
- level in bottle). :
5.3.2.7 Raise hood door.
5.3.2.8 Cl ose CA-V.16.
5.3.2.9 Move sample bottle to shield on cart leaving remote handling tool attached.
5.3.2.10 Close hood.
5.3.2.11 Return to step-off pad with Teletektor, (checking radia-tion levels), check self-reading dosimeters and notify others of radiation levels.
5.3.3 Technician 3 will proceed as follows:
5.3.3.1 Enter Sampling Room CLOSE C A-V-13, CA-V-2, CA-V-110.
5.3.3.2 Move cart to H0T lab.
5.3.3.3 Move sample bottle from shield on cart to shielded area of laboratory bench using remote tool.
- CAUTION: Return to step
_ __ ____ __ _ __ _ ____ ____ _________-o f f pad a n d check do s ime try. :
5.3.3.4 Obtain Teletektor and perform rapid survey o.' Hot Lab.
6.0 FOR USE IN UNIT I ONLY ;