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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
[Table view] |
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METROPOLITA'I EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technien1 Srecification Chansre Recuest No. 38 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 Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
ME'"ROPOLITAN EDISON COMPANY 9 fg By i Vice President-Generation Sworn and subscribed to me this day of @ ,
1976. /
Notaff Public
- 12 .-N,~,,, ~3 i NP?' 514" Espres fe^s, !$, IE/3
.7910290.h/
Fbtropolitan Edison Company (Met-Ed)
Three N11e Island Nuclear Station Unit 1 (Met-Ed)
Operating License No. DPR-50 Docket No. 50-289 i Technical Specification Change Recuest Replace page 3-55 and 3-56 with the attached replacement pages 3-55, 3-56 and 3-56a, and add figures 3.11-1, 3.11-2 and 3 11-3.
Reasons for Proposed Change
. To provide additional safeguards against the possibility of damage to stored spent fuel or syste=s and equip = rat important to safety in the event of a spent fuel cask drop accident.
Our letter GQL 0215 of February 14, 1976 forwarded a detailed evaluation of a postulated spent fuel cask drop accident. Tbis change request addresses those corrective actions outlined in that letter.
Safety Analysis Justifyice Proposed Change This change request imposes more restrictive limits on spent fuel cask covement. Therefore, no unreviewed safety question is involved.
i t
i 1479 064 J
0 0 3.11 HANDLING OF IRRADIATED FUEL Aonlicability Applies to the operation of the fuel handling building crane when within the confines of Unit 1 and there is any spent fuel in storage in the Unit 1 fuel handling building.
i f
l
, Objective i
To define the lift conditions and allowable areas of travel when loads to be lifted and transported with the fuel handling building crane are
- in excess of 15 tons or between 5 to 15 tons or consist of irradiated fuel elements.
Suecification 3.11.1 Spent fuel elements having less than 120 days for decay l of their irradiated fuel shall not be loaded into a spent fuel transfer cask in the shipping cask area.
3.11.2 The key operated travel interlock system for automatically
! limiting the travel area of the fuel handling building crane shall be imposed whenever loads in excess of 15 tons are to be lifted and transported with the exception of fuel handling I
bridge maintenance.
1 3.11 3 a. The lower surface of all loads in excess of 15 tons shall be administratively limited to an elevation six inches or
~
less above the concrete surface at the nominal 3h8 ft-0 in. elevation in the fuel handling building.
- b. During movement of the cask between the carrier and the
, top of the "B" spent fuel pool, the cask vill be restricted l to the transfer path shown in Figures 3 11-1. Administrative l procedures and visual aids will be used to control the cask to the prescribed path. During this transfer the cask lifting yoke shall be oriented in the North-South direction.
- c. During transfer of the cask to and from the cask loading pit, the cask vill be restricted to the transfer path l shown in Figure 3.11-2. Administrative procedures will i be used to ensure that all lateral movements of the cask l are performed at slow bridge and trolley speeds. During l this transfer the cask lifting yoke shall be oriented in j the East-West direction.
I
' d. The Cask decontamination vill be restricted to the shaded areas designated in Figure 3.11-3.
1479 065 3-55
GD GD 3.11.4 Loads in excess of hook capacity shall not be lifted, except for load testing.
3.11 5 Fol]oving =odifications or repairs to any of the load bearing members, i
the crane shall be subjected to a test lift (f 125 perceat of its
! rated load.
l, Bases This specification vill limit activity releases to unrestricted areas resulting
- from damage to spent fuel stor-d in the spent fuel storage pools in the postulated I event of the dropping of a hewry load from the fuel handling building crane.
When a loaded spent fuel transfer cask is moved out of the decontamination pit
- area and along-the centerline of the spent fuel pool's vest vall to the receiving /
, shipping area (Figure 9-18, Section 9), it has a potential drop of 43 feet which is 13 feet greater than its design basis drop. An analysis (1) was performed assuming that the cask and its entire contents of the fuel assemblies are sufficiently damaged as a result of dropping the cask, to allow the escape of all noble gases and iodine in the gap. This release was assumed to be directly to the atmosphere and to occur instantaneously. The site boundary doses resulting from this accident are 5.25 R. whole body and 1.02 R to thyroid, and are within the limits specified in 10 CFR 100.
Specification 3.11.1 required that spent fuel, having less than 120 days decay post-irradiation, not be leaded in a spent fuel transfer cask in order to ensure that the doses resulting from a highly improbable spent fuel transfer l cask drop would be within those calculated above, i
t
! Specification 3.11.2 requires the key operated interlock system, which auto-l matically limits the travel area of the fuel handling crane while it is lifting l and transporting the spent fuel shipping cask, to be imposed whenever loads in excess of 15 tons are to be lifted and transported while there is any spent fuel in storage in the spent fuel storage pools in Unit 1. This automatically l
l ensures that these heavy loads travel in areas where, in the unlikely event of a load drop accident, there vould be less possibility of this event resulting l in any damage to the spent fuel stored in the pools or doing any unacceptable structural damage to the spent fuel pool structure. As described in FSAR Section 9 71.1, the shipping cask area is designed to withstand the drop of t the spent fuel shipping cask from an elevation of 3k9 ft. without unacceptable damage to the spent fuel pool structure.
Specification 3.11.3.a ensures that the lover surface of any heavy load never
. gets higher than six inches above the concrete surface of the 3h8 ft-0 in.
E elevation in the fuel handling building (nominal elevation 3h9 ft-0 in. )
l thereby keeping any i= pact force from an unlikely load drop accident within acceptable limits.
Specification 3.11.3.b and 311.13d restricts the cask transfer path such that a single cask drop accident would not result in unacceptable damage to engineered safeguard circuits located below the cask transfer pr.th.
L l Specification 3.11.3.c restricts the cash transfer path to and from the cask
! loading pit so that the cask vill be tipped in a direction away from the "B" spent fuel pool in the event of a cask drop on the edge of the pool vall.
l t
j (1) FSAR, Supplement 2, Part VII 9 066 l, 3-So i
t Specification 3.11.4 ensures that the prope-c capacity crane hook is used for lifting and transportin6 loads thus reducing . le probability of a load drop accident.
Following modification or repai-s, specification 3.11.5 confirms the load rating of the crane.
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1479 067 3-56a
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. 1479 068 i
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LEGEND-E'(M/X9X TRANSFER PATH 1479 069
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TRANSFER PATH TO AND FROM CASK LOADING PIT.
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