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Category:TECHNICAL SPECIFICATIONS
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 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 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 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 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 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 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 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 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control 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 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 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 ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage 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 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 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 ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] 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
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER 6 LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 uperating License No. DFR-30 Docket No. 50-289 Technical Spa:ification Change Request No. 13 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear S tation Unit 1.
METROPOLITAN EDISON COMPANY By /
Vice President-Generation Sworn and subscribed to me this /3 day of , 1975 7
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Notary ?ublic R'0PARO !. R'JTH Ne- , F _ - 2 T <; . E:rk: Co.
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METROPOLITAN EDISON COMPANY PO3T OFFICE BOX 542 RE ADING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 June 13,1975 GQL llh8 Mr. Charles P. Hoy, Chairman Board of County Commissioners of Dauphin County P.O. Box 1295 Harrieburg, Pennsylvania 17120
Dear Mr. Hoy:
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Enclosed please find one copy of Technical Specification Change Request No. 13 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1.
This request was filed with the U. S. Nuclear Regulatory Commission on June 13, 1975.
Very truly yours ,
/s/ R. C. Arnold R. C. Arnold Vice President RCA:RSB:pa File 20.1.1/7. 7.4.3.6.1 1492 263
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l METROPOLITAN EDISON COMPANY suss:caavoice.vepavusuc inunesconroaanon TELEPHONE 215 - 929 3601 POST OFFICE BOX 542 REAOf NG, PENNSYLVANIA 19603 June 13, 1975 GQL 11h7 Mr. Weldon B. Archart, Chairman Board of Supervisors of Londonderry Township R.D. #1 Geyers Church Road Middletown, Pa. 17057
Dear Mr. Arehart:
Enclosed please find one copy of Technical Specification Change Request No. 13 to Appendix A of the Operating License for Ihree Mile Island Nuclear Station Lhit 1.
This request was filed with the U. S. Nuclear Regulatory Cocmission on June 13,1975.
Very truly yours,
/s/ R. C. Arnc1d R. C. Arnold Vice President RCA:RSB:tas File: 20.1.1 / 7.7.4.3.6.1
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1492 264
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UNITED STATES OF AMERICA U. S. NUCLEAR REGULATORY COMMISSION IN l'4E MATTER OF DOCKET NO. 50-289 OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Srecification Change Reque e No.13 to Appendix A of the Operating License for Three Mile Island Nuc1aar Station Unit 1, dated June 13, 1975, and filed with the United States Nuclear Regulatory Commission on June 13, 1975, has this the thirteenth day of June 1975 been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and Dauphin County, Pennsylvania, by deposit in the United States mail, addressed as follows:
Mr. Weldon B. Arehart, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Londonderry Board of County Commissioners of Township Dauphin County Township Building Dauphin County Courthouse R. D. #1, Geyers Church Road P. O. Box 1295 Middletown, Pennsylvania Harrisburg, Pennsylvania METROPOLITAN EDISON COMPANY By /s/ R. C. Arnold Vice President 1492 265
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Metropolitan Edison Co=pany Three Mile Island Nuclear Station Unit I Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Recuest 13 Licensee requests that the following pages be added to Appendix A of Tech-nical Specifications. The proposed specifications have been assigned speci- '
fication and page numbers in accordance with those previously submitted in our Change Request 7 dated January 30, 1975 Pages 3-67, 3-68. Add new Specification 3.16.
Pages h- 59, h-60. Add new Specification 4.16.
A copy of proposed new pages marked " Change Request No.13" is aotached.
Reason for Protosed Changes This change request was initiated in response to a request made by the Cc= mis-sion's Mr. Getrge Lear as stated in his letter dated May 7,1975, and if i=ple-mented, veuld serve to provide additional assurance that the operational capa-bilities of the existing vent header system are fully realized.
Safety Analysis Justifying Change As the chLnge reflects additiona: ad more stringent requirements than those presently existing, there exist no unreviewed safety questions. It should also be noted that it is the Licensee's position that the changes as contained herein, in conjunction with the pr >cedural revisions that have been made to strengthen existing adminstrative controls (Ref: Letter from Licensee to Com-mission's Mr. George Lear, dated April 19, 1975 {GQL 0951}), together provide sufficicnt additional measures to prevent a recurrence of the type of unplanned radioactive releases referenced in Mr. Lear's March 19, 1975 letter.
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Change Request No. 13 3.16 WASTE ^-AS VENT HEADER SYSTEM Auplicability Applies to the operation of the Waste Gas Vent Header System.
Objective To minimize unplanned gaseous releases from the Waste Gas Vent Header System.
Specification 3.16.1 If the Vent Header pressure is greater than 2.0 psig, a deter-mination shall be made that the vaste gas system co= pressors are operating.
3.16.2 At least .; Waste Gas Compressor shall be operable at all times and automatically interlocked to start if the vent header pressure exceeds 1.8 0.2 psig. If neither vaste gas compressor is operable and vent header pressure exceeds 2.1 psig, an orderly shutdown to the hot shutdown condition shall be commenced within eight hours.
3.16.3 The water levels within the vent header system loop seals shall normally be maintained at sufficient elevations to pre-vent releases of gas from the vent header for vent header pressures equal to or less than 2.8 psig. The vent header system loop seals consist of the loop seal for the miscel-laneous vaste storage tank and the reactor coolant bleed tanks and the loop seal for each reclaimed boric acid storage tank. If the specified water level drops below the level required for 2.8 psig (78 in.), adequate level shall be re-stored within 2h hours.
3.16.h The loop see.1 for the Reactor Coolant Waste Evaporator and the loop seal for the Miscellaneous Waste Evaporator shall be kept plugged until such time as per=anent modifications to these seals are made.
Bases The Waste Gas Vent Header System co71ects radioactive gases which are evolved from the liquids in various liquid easte system tanks. These gases are pumped into one of three gas decay tanks oy either of two vaste gas compressors.
These compressors come into operation when the vent header pressure is 1.8 psig (equivalent to 16.5 psia.). In addition, relief valves are provided, which discharge to the unit stack when system pressure is 2.2 psig, and local loop seals are provided for the various tanks. Five relief seals provide pressure relief at a system pressare of approximately 2.8 psig.
As of date of preparation of these specifications, the demonstrated operational capability of the Waste Gas Vent Header System is not sufficient so as to assure prevention of nor=al operating system pressure transients from causing unplanned 3-67 l 4 92 2i-[
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Change Request No. 13 situations wherein the system relief valves lift and/or system associated loop seals are blown and unplanned radioactive gaseous I;' eases occur. Therefore, until such time as a design modificaticn can be impleme ted to increase the operational capability of the system,it is advisable to implement additional specifications so as to better ensure that the full operational capabilities of the existing system are realized.
It is also pertinent to note that two of the system associated loop seals have in themselves ber" designated to be inadequate and that these two sub-ject seals consist of one for the Reactor Coolant Waste Evaporator and the one for the Miscel. sous Waste Evaporator. Therefore, until such time as these seals and/or associated systems can be modified, it is also advisable to implement additional specifications so as to ensure that the two subject seals are maintained in a plugged condition.
In particular, these Specifications are intended to do the following:
Ensure that vent header pressure is maintained at or below its normal upper upper limit of 1.8 psig, and ensure that the ability of the compressors to pump gases into the decay tanks is verified whenever the pressure alarm point of 2.0 psig is reached.
Ensure availability of one compressor so that it will come into opera-tion when required.
Ensure that adequate water is maintained within the tank loop seals (see Technical Specification h.17 for a definition of the required water level).
Ensure that the two loop seals which were previously plugged to pre-vent inadvertent gas releases vill remain plugged until their design can be appropriately modified.
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1492 268 3-68
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Change Request No. 13 h16 WASTE GAS VENT HEADER SYSTEM Aunlicability Applies to surveillance of the Waste Gas Vent Header System.
Objective To identify surveillance requirements to minimize unplannod gaseous releases from the low pressure vent header until permanent modifications are made to allow the vent header to absorb greater pressure transients.
Specification h.16.1 A check of loop seal water shall be performed on a daily basis to verify that the water level is at the required height above the bcctom of the seal, k.16.2 Both vaste gas compressors shall be checked for operability every month.
4.16.3 Automatic startup of each vaste gas compressor on application of a test signal simulating vent hea' der system pressures of equal to or greater than 1.8 0.2 psig shall be checked on a semiannual basis.
Bases The height of water within the loop seals is selected to ensure that releases of gas vill not occur from these seals when vent header system pressure is equal to or less than 2.8 psig. This pressure corresponds to a water height of 78 inches, which is within six inches of the total available seal height.
This required height is defined by:
h = 39 + P x lh in/psig h = required height, inches p = vent header operating pressure, psig.
Each loop seal is essentially a "u-tube", with its upstream leg connected to a liquid vaste system tank. A sight glass is provided to indicate the level of water in the downstream leg of the seal. The required water levels which are applicable to the measured values in the downstream leg of the seal, ensure that a gas release vill not occur if vent header system pressure increases from its operating pressure to a pressure of 2.8 psig.
Operation of the vaste gas compressor is required to pu=p out excess quantities of gas which may be collected in the vent header system. These compressors come into operation periodically. Specification h.17.2 ensures that their operability is checked monthly.
This check may consist of observing normal co= pressor operation, or may consist of manual initiation of compressor operation if the compressor were not normally in use during the monthly period. This check vill be considered satisfactory if h-59
vnange Request No. 13 the compressor motors are observed to be operating.
A semiannual test verifies the operability of the controls which initiate automatic startup of the compressors, and to check the pressure setpoint for their automatic startup.
This check vill be considered satisfactory if the compressor motors are observed to ecce into operation when a signal si=ulating a pressure of 1.8 psig is applied.
Specification h.17.h ensures that frequent surveillance is made of the vent header system pressure.
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e 1492 270 h-60