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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20059D1621993-12-28028 December 1993 Amend 48 to License DPR-73,extensively Modifying TMI-2 App a & B TSs Consistent W/Plans for post-defueling Monitoring Storage of Facility ML20062K0951993-12-0606 December 1993 Amend 47 to License DPR-73,deleting Definition of Agw & Current App TS Limiting Condition of Operation Re Disposal of Agw Using Processed Water Disposal Sys ML20059K2921993-11-0808 November 1993 Amend 46 to License DPR-73,modifing Section 3.9.12, Fuel Handling Building/Auxiliary Building Air Cleanup Sys & Associated Bases ML20128P7101993-02-19019 February 1993 Amend 171 to License DPR-50,revising TS Section 6.3 to Incorporate Requirements Prescribed by 10CFR55 ML20058G1291990-11-0606 November 1990 Amend 39 to License DPR-73,modifying Tech Specs Re Administrative Requirements Associated W/Periodic Audits ML20247L0371989-09-11011 September 1989 Amend 35 to License DPR-73,modifying Tech Specs by Deleting Prohibition Imposed by Tech Spec 3.9.13 & on Disposal of Accident Generated Water ML20247G3971989-05-15015 May 1989 Amend 34 to License DPR-73,revising Tech Specs Re Fire Protection Sys ML20245J1121989-04-27027 April 1989 Amend 149 to License DPR-50,changing Reactor Coolant Temp Setpoint,Correcting Error Resulting from Oversight in License Amend 142 & Clarifying Number of Requirements & Bases ML20245A6511989-04-12012 April 1989 Amend 33 to License DPR-73,modifying App B Tech Specs by Revising Certain Surveillance Terms & Definitions Consistent W/Meaning & Usage in App a Tech Specs ML20195B6881988-05-27027 May 1988 Amend 30 to License DPR-73,modifying Tech Spec Sections 1,2, 3,3/4 & 6 to Align License Requirements W/Plant Conditions ML20155B3101988-05-25025 May 1988 Amend 30 to License DPR-73,modifying App a Tech Specs Sections & Revises Tech Specs Aligning Licensing Requirements to Appropriate Current,As Well as Future,Plant Conditions Through Current Cleanup Operations NUREG-0742, Amend 29 to License DPR-73,revising Table of Contents & Sections of App B to Modify Radiological Environ Monitoring Program to Be Consistent w/NUREG-07421988-03-17017 March 1988 Amend 29 to License DPR-73,revising Table of Contents & Sections of App B to Modify Radiological Environ Monitoring Program to Be Consistent w/NUREG-0742 ML20234B9561987-06-25025 June 1987 Amend 28 to License DPR-73,modifying Tech Specs to Require NRC Approval of Only Those Procedures & Changes Which Alter Distribution or Processing of Radioactive Matl Which Could Cause Releases Exceeding Design Objectives ML20212Q7221987-04-17017 April 1987 Amend 27 to License DPR-73,revising Tech Specs to Delete All Operability Requirements for Emergency Diesel Generators & Modifying Operability Requirements for Control Room Emergency Air Cleanup Sys ML20140F8351986-03-14014 March 1986 Amend 114 to License DPR-50,changing Tech Spec to Authorize Operation at Steady State Reactor Core Power Levels Not to Exceed 2,535 Mwt ML20133M3951985-10-21021 October 1985 Amend 25 to License DPR-73,changing Section 2.1.2 Re Gaseous Effluents of App B Tech Specs.Epithet Used to Describe Testing of Radiation Vent Monitors Changed to Instrument Functional Test to Achieve Consistency in Tech Specs ML20147A9961978-09-19019 September 1978 Amend 44 to DPR-50,revising Tech Specs Re Completion of Facility Mod for Fire Protection ML20150F3821978-05-19019 May 1978 Amend 40 to License DPR-50,reducing Allowable Measured Neutron Flux Tilt,Allowable Axial Power Imbalance & Allowable Position Limits for Axial Power Shaping Rods 1999-07-08
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,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 ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,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 ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 1999-08-20
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- o pn rerg y* t UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055H001 4 ,o 9*****
GPU NUCLEAR. INC I
DOCKET NO. 50-320 I
THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 I AMENDMENT TO POSSESSION-ONLY LICENSE Amendment No. 51 License No. DPR-73 )
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l 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by GPU Nuclear Corporation (GPUN or licensee) dated February 16, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), !
and the Commission's rules and regulations as set forth in 10 CFR I Chapter I; l
B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted t
in compliance with the regulations of the Commission; I D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this cmendment is in accordance.with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied.
I 9610300298 961024 PDR ADOCK 05000320 i P PDR l
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i 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(1) of possession-Only No. DPR-73 is hereby amended to read as follows:
(1) Technical Specifications The Technical Specifications, as revised through Amendment No. 51, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to the date of the possession only license.
- 3. This license amendment is effective as of the date of issuance. I FOR THE NUCLEAR REGULATO COMMISSION l p ,
{
Seymour H. Weiss, Direct ;
Non-Power Reactors and Decommissioning i Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical I Specifications Date of Issuance: October 24, 1996 I l
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ATTACHMENT TO LICENSE AMENDMENT NO. 51 POSSESSION-0NLY LICENSE NO DPR-73 DOCKET N0. 50-320 i Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
l REMOVE INSERT 3/4.0-1 3/4.0-1 3/4.1-4 3/4.1-4 B3/4.0-1 83/4.0-1 83/4.0-2 B3/4.0-2 l
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3/4.0 LIMITING CONDITIONS FOR PDMS AND SVRVEILLANCE REQUIREMENTS l 3/4.0 APPLICABILITY l
l LIMITING CONDITIONS FOR PDMS t
! 3.0.1 Limiting Conditions for PDMS and ACTION requirements shall be l applicable during POST-DEFUELING MONITORED STORAGE or other conditions specified for each specification.
3.0.2 Adherence to the requirements of the Limiting Condition for PDMS and/or l associated ACTION within the specified time interval shall constitute i compliance with the specification. In the event the Limiting Condition for PDMS is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.
l 3.0.3 In the event a Limiting Condition for PDMS and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those !
addressed in the specification, initiate appropriate actions to rectify the '
problem to the extent possible under the circumstances and submit a report to ,
the Commission pursuant to the requirements of 10 CFR 50.73. l l \
! SURVEILLANCE REQUIREMENTS l
4.0.1 Surveillance Requirements shall be met during PDMS or other conditions specified for individual Limiting Conditions for PDMS unless otherwise stated in an individual Surveillance Requirement. i 4.0.2 Each Surveillance Requirement shall be performed within the specified i
time interval with a maximum allowable extension not to exceed 25% of the l surveillance interval.
l 4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a l Limiting Condition for PDMS. Exceptions to these requirements are stated in the individual Specifications. Surveillance Requirements do not have to be performed on inoperable equipment.
l 4.0.4 If it is discovered that a surveillance was not performed within its l specified frequency, then compliance with the requirement to declare the LC0 not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.
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i Three Mlle Island-Unit 2 3/4.0-1 Amendment 51 1
l CONTAINMENT AIR LOCKS LIMITING CONDITIONS FOR PDMS l 3.1.1.3 Each Containment Air Lock shall be OPERABLE with at least one door closed except when the air lock is being used for transit entry and exit in accordance with site-approved procedures.
APPLICABILITY: PDMS ACTION:
With no Containment Air Lock door OPERABLE, restore at least one door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I SURVEILLANCE RE0VIREMENTS '
4.1.1.3 Each Containment Air Lock shall be demonstrated OPERABLE annually by performing a mechanical operability check of each Air Lock Door, including a visual inspection of the components and lubrication if necessary and by visually inspecting the door seals for significant degradation. When both Containment Air Lock doors are opened simultaneously, verify the following conditions:
- a. The capability exists to expeditiously close at least one Air Lock door; ,
- b. The Air Lock doors and Containment Purge are configured to restrict the outflow of air in accordance with site-approved procedures; and
- c. The Air Lock doors are cycled to ensure mechanical operability within seven days prior to opening both doors.
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i j Three Mile Island - Unit 2 3/4.1-4 Amendment 51 l
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3/4.0 APPLICABILITY i BASES l i l
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The specifications of this section provide the general requirements applicable '
l to each of the Limiting Conditions for PDMS and Surveillance Requirements l l within Section 3/4.
l 3.0.1 This specification defines the applicability of each specification in terms of PDMS or other specified conditions and is provided to delineate specifically when each specification is applicable.
l 3.0.2 This specification defines those conditions necessary to constitute i
compliance with the terms of an individual Limiting Condition for PDMS and associated ACTION requirement.
3.0.3 The specification defines the action and reporting requirements for those circumstances where the ACTION statement for Limiting Conditions for PDMS was exceeded.
4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for PDMS are met and will be performed during the condition for which the Limiting Conditions for PDMS are applicable.
4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal I surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent l
surveillance activities. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified. The allowable tolerance is based on engineering judgement and the
, recognition that the most probable result of any particular surveillance being i performed is the verification of conformance with the Surveillance l Requirements. This provision is sufficient to ensure that the reliability l ensured through surveillance activities is not significantly degraded beyond I
that obtained from the specified surveillance interval.
l 4.0.3 The provisions of this specification set forth the criteria for l determination of compliance with the OPERABILITY requirements of the Limiting Conditions for PDMS. Under this criteria, equipment, systems or components l are assumed to be OPERABLE if the associated surveillance activities have been l satisfactorily performed within the specified time interval. Nothing in this I provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.
Three Mile Island - Unit 2 B3/4.0-1 Amendment 51 l
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3/4.0 APPLICABILITY (Con't)
BASES 1
4.0.4 This specification establishes the flexibility to defer declaring l affected equipment inoperable or an affected variable outside the specified limits when a surveillance has not been completed within the specified l frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> applies from the point in time
, that it is discovered that the required surveillance nas not been performed and not at the time that the specified frequency was not met.
The delay period provides an adequate time to complete surveillances that have been missed. This delay period permits the completion of a surveillance before complying with required actions or other remedial measures that might preclude completion of the surveillance.
The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the surveillance, the safety significance of the delay in completing the required surveillance, and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements.
When a surveillance with a frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, this provision allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the surveillance.
Failure to comply with specified surveillance frequencies is expected to be an infrequent occurrence. Use of the delay period is not intended to be used as an operational convenience to extend surveillance intervals.
If a surveillance is not completed within the allowed delay period, then the l equipment is considered inoperable or the variable is considered outside the specified limits and the completion times of the required actions for the applicable LCO conditions begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the completion times of the required actions for the applicable LCO conditions begin immediately upon failure of the surveillance.
Completion of the surveillance with the delay period allowed by this specification, or within the completion time of the actions, restores compliance.
Three Mile Island - Unit 2 B3/4.0-2 Amendment 51 l