Amend 8 to 790912 Restart Rept Providing Addl Info Re Solid Waste Disposal Sys,Mobile Solidifation Sys,Plant Sheilding & Auxiliary Bldg Ventilation SysML19260B018 |
Person / Time |
---|
Site: |
Three Mile Island ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
12/04/1979 |
---|
From: |
METROPOLITAN EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML19260B015 |
List: |
---|
References |
---|
NUDOCS 7912060349 |
Download: ML19260B018 (5) |
|
|
---|
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 REPORT
MONTHYEARML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20063A4001993-12-31031 December 1993 TMI-1 Cycle 10 Startup Rept ML20058P0041993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept ML20092A5221992-02-0404 February 1992 TMI-1 Cycle 9 Startup Rept ML20043G2481990-04-30030 April 1990 TMI-1 Cycle 8 Startup Rept. W/900612 Ltr ML20196E8591988-12-0505 December 1988 TMI-1 Cycle 7 Startup Rept ML20236H3781987-10-0909 October 1987 App I TMI-1 1987 Reactor Bldg Local Leak Rate Testing Rept, Updated-871009, for 861104-870318 ML20237J8141987-08-21021 August 1987 TMI-1,Cycle 6 Startup Test Rept ML20214L9471987-04-13013 April 1987 Analysis of Dose Rate Under TMI-2 Reactor Vessel ML20210S0231986-11-30030 November 1986 Reactor Containment Bldg Integrated Leak Rate Test ML20214P9891986-09-15015 September 1986 TMI-2 In-Core Nozzle Evaluation ML20197H3411986-04-24024 April 1986 Gpu Nuclear TMI-1 Startup Rept for Restart ML20138F9381985-10-18018 October 1985 Rev 0 to Control Bldg `Delta-P' Test Single Mode Failure (Postulated) of Dampers (AH-D-37,41A & 28) & Airflow Measurements ML20100K8271985-03-28028 March 1985 Rev 0 to Adequacy of TMI-1 Once-Through Steam Generator Return to Svc Safety Assessment After 1984 Tech Spec Eddy Current Test Exam ML20100K7991985-03-0505 March 1985 Rev 1 to Evaluation of 1984 Required Tech Spec Exam for TMI-1 Once-Through Steam Generator ML20126B7581984-06-20020 June 1984 Rev STR-1 to RCS Leak Rate Verification Test Supporting Documentation Encl ML20090H2981984-04-30030 April 1984 TMI-1 Reactor Containment Bldg Integrated Leak Rate Test ML20091Q8441984-04-10010 April 1984 Rept on Fire Resistant Cables ML20091Q8471984-02-17017 February 1984 Fire Resistance Testing of Fire Resistant Cables ML20126C1281983-09-14014 September 1983 Rev 2 to Technical Data Rept 417, TMI-1 Once-Through Steam Generator Repair ML20126B9301983-05-11011 May 1983 Rev 3 to Technical Data Rept 388, Mechanical Integrity Analysis of TMI-1 Once-Through Steam Generator Unplugged Tubes ML20126B6581982-12-0909 December 1982 Rev 0 to Technical Data Rept 388, Mechanical Integrity Analysis of TMI-1 Once-Through Steam Generator Tubes. Supporting Documentation Encl ML20063K0421982-06-25025 June 1982 App C to TMI-1 Steam Generator Recovery Program,Task 7, Primary Sys Review,Rcs Insps & Requalification, Exam Results ML20070H5181982-06-0303 June 1982 Exam of TMI-1 Reactor Vessel O-Ring & Control Rod Drive Mechanism Closure Insert, Final Rept ML20070H5091982-05-20020 May 1982 TMI-1 Recovery:Regenerative Neutron Source Retainer Exam ML20042B8631982-03-0808 March 1982 Stress Analysis for Demonstration of Operability of Purge & Vent Valves During Dba. ML20004E4261981-06-11011 June 1981 Amend 23 to Restart Rept ML19350B7501981-03-18018 March 1981 Amend 24 to Restart Rept ML20004E4281981-02-15015 February 1981 Analysis of Two Phase Flow Induced Differential Pressure Across TMI-1 Pressurizer Safety Valve Line Elbow Taps. ML20113G3871980-11-20020 November 1980 Qualification Insp of Series 24 Circuit Breaker Control Switch to ESC-STD-1000,Rev 1 ML20062J3781980-10-17017 October 1980 Amend 22 to TMI-1 Restart Rept ML19337B5861980-10-0303 October 1980 Amend 21 to Restart Rept ML19331D1301980-08-0808 August 1980 Amend 20 to Rept in Response to NRC Recommended Requirements for Restart of TMI-1. ML19331D1731980-08-0404 August 1980 Amend 19 to Restart Rept ML19323G3401980-05-23023 May 1980 Amend 18 to Restart Rept Providing Addl Info ML19305D6091980-04-14014 April 1980 Corrected Page 2.1-45,Amend 13,to Restart Rept,Describing short-term Mods ML19305D6621980-04-11011 April 1980 Amend 16 to Restart Rept, Providing Addl Info Re Plant Mods ML19323A0591980-04-0303 April 1980 Amend 17 to Restart Rept, App 7A,Revision 2 to Radiation Protection Plan ML19305C7011980-03-28028 March 1980 Amend 15 to Restart Rept,Consisting of Proprietary Version of BAW-1601, Pilot Operated Relief Valve (PORV) Monitor Test & Flow Detectors for Pressurizer Code Safety & Porvs. BAW-1603 Withheld (Ref 1OCFR2.790) ML19290E0131980-03-0303 March 1980 Amend 13 to Restart Rept ML19296B4801980-02-15015 February 1980 Amend 12 to Restart Rept for TMI-1 ML19257D3731980-01-31031 January 1980 Amend 11 to TMI-1 Restart Rept. ML19260C7361980-01-0404 January 1980 Amend 10 to Restart Rept,Providing Addl & Nonsubstantive Administrative Changes to Emergency Plan ML19260C0311979-12-14014 December 1979 Amend 9 to 790912 Startup Rept ML19260B0181979-12-0404 December 1979 Amend 8 to 790912 Restart Rept Providing Addl Info Re Solid Waste Disposal Sys,Mobile Solidifation Sys,Plant Sheilding & Auxiliary Bldg Ventilation Sys ML19260B0191979-12-0404 December 1979 Revised Section 5.2 of TMI-1 Restart Rept Re Station Organization ML19210E5801979-12-0303 December 1979 TMI-1 Restart Rept, Amend 7 ML19210E1401979-11-28028 November 1979 Amend 6 to 790912 Restart Rept ML19254D7301979-10-26026 October 1979 Amend 3 to Restart Rept,Providing Addl Info 1997-12-31
[Table view] |
Text
-- - - - - -
handle the waste generated from a single operating unit anc TMI-1 operated successfully in the single unit mode in excess of three years during TMI-2 cc_struction. The TMI-2 design utilizec the conservation of the TMI-1 system to provide racwaste treatment capabilities for liquid racwaste generatec from its operation.
Therefore, all TMI-2 liquid racwaste had to be transf erred to TMI-1 for treatment. Therefore isolation of the units will increase the TMI-1 liquid radwaste capability relative to that available during the pre-accident period . The Miscellaneous Waste Evaporation is the primary process equipment used to treat liquic raowaste.
The evaporator has been used successfully in the past for a single unit waste treatment requirements. Because of interferences in TM1-1 causec by the storage of IMI-2 waste waters, the evapora-tion is not currently in use. At the time of startup of TMI-1 (or within the month previous to starting) the evaporation will be shown to be operational or replacement equipment shall be available to supplement evaporation operation.
Although, TMI-1 radwaste processing capabilities are currently limited by the presence of TMI-2 liquid radwaste storea in TMI process vessels, this limitation will be completely re - , by transferring and flushing all TMI-2 waste storea in TMI . .o TMI-2 facilities prior to startup. TMI-2 miscellaneous liquid radwaste will be processed in sys ems installed (or to be installed) in accordance with the recovery effort. The systems include Epicor 2, the submerged demineralizer system and an evaporator / solidification system.
A complete desertption of the TMI-I radtasts treatment system capability is provided in section 7.3.1.. 4 of this report.
7.2.4 Solid Waste Disposal Prior to the accident, TMI-2 radwaste system was completely cepencent on TMI-1 facilities for solid waste processing and disposal of evaporation concentrates, spent resin and compactible trash.
Isolation of the two units will enhance the ability of TMI to process solid radwaste. TMI-2 had installed separate trash compact-ing equipment and will obtain the equipment to solidify liquia anc wet solid waste as part of the recovery program. Thl-1 capabilities are not r quired for the TMI-2 recovery program. THI-1 currently has an opeating trash compactor used exclusively for TMI-1 trash.
Solicification facilities will be available through the use of a contractor for the short term and subsequently through the use of a discussed more thoroughly in Supplement 1, part 2, response to Question 53 and Section 7.3.1.3.
7.2.5 Sanftary Facility Drains By design, sewage and sanitary drains from TMI-2 would join those from IMI-1 at the sewage pumping station and then be treated in a common sewage treatment plant. Operationally, the sewage from the individual unit currently remain separate 1520 220 7-4 Am. 8 7 0120 60 34-9
B. The Auxiliary and Fuel Handling Building Ventilation Systems and the Reactor Building Purge System The auxiliary and fuel handling building ventilation systems and the reactor building purge systems serve primarily to distribute to end exhaust ventilation i air from *.he areas indicated.
7.3.1.3 Selid Waste System !
7.3.1.3.1 General:
i i
Five general types of waste are produced, processed and shipped from the TMI-1 as solid radioactive waste. These wastes are:
- a. Concentrated Liquid Waste (evaporstor bottoms)
- b. Used Precoat (spent powdered resin) ;
- c. Spent Resin (bead type) i
- d. Dry Compactible Trash I
- e. Dry Non-Compactible Trash Dry trash is shpped offsite directly (i.e. , without solidification) I following compaction (to reduce the volume) where possible. TMI-1 has a trash compactor for use with 55 gallon drums dedicated for the exclusive use of the unit. Trash is segregated during collection to insure that TMI-1 and TMI-2 wastes remain separate. Appropriate packaging of dry trash is performed in accordance with applicable shipping and disposal regulations.
Concentrated liquid waste, used precoat, and spent resin will be solidified prior to being shipped offsite for disposal where required by the TMI-1 Technical Specifications and applicable regulations.
Permanently installed plant equipment does not current exist to solidify radwaste.
A two part program has been initiated to solidify these wastes.
For the short term, until the permanent system is available, TMI-1 will use contractor supplied mobile solidification systems. A permanent solidification system using a chemical process developed by Dow Chemical will be installed to replace the mobile systems and is expected to be available by January 1, 1981.
7.3.1.3.2 Mobile Solidification Systems Two specific mobile solidification systems are being considered for use in TMI-1. Niether of the systems considered use urea formaldehyde (UF) as a solidification agent and neither system is subject to the free water problems associated with UF. The systems considered are the Hittman Nuclear and Development Corporation cement in-cask system and a demonstration rystem from Dow Chemical. A Procass Control Program (PCP), approved by the USNRC is required to be available prior to the operation of any radwaste solidification system.
Systems other than the two specifically noted may be considered depending on their ca y ability, availability, and approval of an applicable PCP.
1520 221 7-11a Am. 8
The two mobile systems are described below:
Mobile Dow Solidification System .
I A prototype of a Dow Sclidification System previously used to i demonstrate the process at nuclear plants is available on a rental basis. The system encapsulates tiny droplets of waste material within a hard organic polymer matrix. The equipment consists of i an air driven mixer and fill head anc can be used with 55 gallon l drums.
Prior to beginning actual full scale solidification, the ratios of ,
the chemicals used are determined through laboratory scale trial ,
solidification. The drums are first partially filled with the ?
appropriate amount of the D0h' binder, a modified vinyl ester resin.
The mixer is placed in the drum and started. Waste is slowly added ,
and thoroughly mixed to achieve an emulsion of the two materials. I Small quantities of two other chemicals are added to the emulsion l to initiate and control the solidification of the binder. r This process may be used to solidify evaporator bottoms and used precoat but not spent resin. Although the system can solidify bead resins, there is insufficient radiation shielding available l
to protect personnel in the vicinity of the process. Complete remote l operation is not possible. !
The full drum radiation levels expected are:
Evaporator bottoms < 500 mr/hr Used precoat < 2 r/br Spent resin 10-30 ichr Hittman In-Cask Cement Solidification System A solidification system availabla from Hittman uses cement to solidify all three types of waste in a pre-shielded container.
The shielding will be sufficient to protect operating personnel while solidifying spent resin. A disposal liner with an internal mixer is used as the solidification container. The ratios of cement, additives (if required) and waste that will produce a dry product are determined through test solidification in a laboratory in accordance with the PCP.
The quantity of waste to be solidified is pumped into the liner.
(Bead resin may be dewatered to reduce the wast volume.) The mixer is started and cement is added. Mixing is continued until the mixer motor current increases indicating the mixture is beginning to " set". Following visual and tactile verification of solidification the liner and cask are closed and shipped.
1520 2'd d
7-11b Am. 8
Solidification Process Rates '
f DOW Evaporator Bottoms 100 cwft/ day Used Precoat 50 cwft/ day Spent Resin N/A
!!ITTMAN Evaporator Bottoms 200 cwft/ day ,
Used Precoat 100 cwft/ day
- Spent Resin 100 cwft/ day i i
i Radwaste Production Rate !
l Evaporator Bottoms 20 cwft/ week ;
Used Precoat < 1 cwft/ week Spent Resin < 5 cwft/ week Storage Capacity Evaporator Bottoms 1456 cwft Used Precoat 300 cwft Spent Resin 500 cwft Schedule of Doerability Dow Mobile System February 1, 1980 Hittman January 1, 1980*
- Depending on the approval of the PCP.
The quantity of each of the waste types that require solidification, on site at the time of TMI-1 startup will be less than 50% of the designed storage capacity.
1520 223 7-11c Am. 8
7.3.2 Plant Shielding 7.3.2.1 General:
The purpose of this section is to identify the necessary action to be taken for providing additional shielcing, procr: ures or plant modifications in vital areas and to equipment in which personnel occupancy may be unduly degraced by the large raciar, ion fielas in operating these systems in a post-accident environ'aent.
Systems, components, and areas consicered subject to post-accicent large radiation fields include: decay heat removal, reactor building spray recirculation, make-t; and let-down, wacte gas, Rad Waste Control Center, and Liquid and Gas Waste Panel.
7.3.2.2 Design Review:
In order to determine which areas and systems require additional shield-in or plant modifications, a review of existing design will be completed which will identify and recommend the cor-rective actions needed in vital areas throughout the Unit.
The review will encompass the accessibility and operability of the above stated systems and area in a post-accident environment.
Bases to be used in comparing present design to post-accicent environment. Bases to be used in comparing present design to post-accident radiation levels will be the fission product relacce as describec in Regulatory Guices 1.3 and 1.4. The cesign review will be completed by January 1,1980.
7.3.2.3 Near Term Modifications:
Those near term modifications, identified by the cesign review, will be completed prior to startup of Unit 1.
7.3.2.4 Long Term Modifications:
Over the longer term modifications not completec before startup of Unit I will be completed by January 1,1981.
7.3.3 Auxiliary Building Ventilation System 7.3.3.1 General The Unit-1 Auxiliary Building Ventilation System is combinen with the Fuel Hancling Building Ventilation System prior to filtration 1520 22s 7-12 Am. 8
.