Similar Documents at Perry |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211P2871999-09-0909 September 1999
Proposed Tech Specs Pages,Increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal
ML20216E4631999-09-0909 September 1999
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Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons
ML20210M7851999-08-0404 August 1999
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ML20196A2021999-06-17017 June 1999
Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp
ML20204E4971999-03-15015 March 1999
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Proposed Tech Specs Improving Licensing & Design Basis for Isolation of FW Penetrations
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Proposed Tech Specs Improving Licensing & Design Basis for Isolation of Feedwater Penetrations
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Proposed Tech Specs 2.1.1.2,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by GE
ML20155D8241998-10-27027 October 1998
Proposed Tech Specs Adding Two Paragraphs to TS 5.2.2.e, Organization - Unit Staff
ML20151V4831998-09-0909 September 1998
Proposed Tech Specs Stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Check Valves Do Not Need to Be Included in Hydrostatic Program
ML20151V1111998-09-0303 September 1998
Proposed Tech Specs Permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allowing Performance of EDG 24-hour TS SR Test in Modes 1 & 2
ML20151V6861998-09-0303 September 1998
Proposed Tech Specs Increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Volume Due to Vortex Formation at Eductor Nozzles Located in Fuel Oil Storage Tank
ML20151S9561998-08-31031 August 1998
Proposed Tech Specs,Allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable
ML20236T7911998-07-22022 July 1998
Proposed Tech Specs Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys
ML20151P1921998-07-13013 July 1998
Proposed Tech Specs,Increasing Present +/- 1% Tolerance on Safety Mode Lift Setpoint for SRVs to +/- 3%
ML20236H8411998-06-30030 June 1998
Proposed Tech Specs,Increasing Boron Concentration in Standby Liquid Control Sys for Pnpp Cycle 8 Fuel Design & Providing Margin for Future Cycles as Required
ML20216H9361998-04-14014 April 1998
Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996
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Proposed Tech Specs,Revising 3.8.1 Re AC Sources to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs
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Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7
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Proposed Tech Specs 5.2.2.e,removing Reference to NRC Policy Statement on Working Hours.Rev Allows Changes to Specific Overtime Limits & Working Hours to Be Evaluated IAW 10CFR50.59, Changes,Tests & Experiments
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Proposed Tech Specs,Revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys
ML20148A6871997-05-0202 May 1997
Proposed Tech Specs Re Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria
ML20137S7761997-04-0909 April 1997
Proposed TS Requirements 3.9.1.1 & 3.9.2.2 Re Frequency on Refueling Equipment & one-rod-out Interlocks
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Proposed Tech Specs 1.1 Re definitions,3.6.1.1 Re Primary Containment - operating,3.6.1.2 Re Primary Containment Air locks,3.6.1.3 Re PCIVs,3.6.5.1 Re Drywell & 5.5 Re Programs & Manuals
ML20134D8751996-10-24024 October 1996
Proposed Tech Specs 2.1.1.2,safety Limits Applying Conservatism by Increasing MCPR Safety Limit Values
ML20117E7891996-08-27027 August 1996
Proposed Tech Specs,Revising Mls Leakage Requirements & Eliminating MSIV Control Sys
ML20108A2581996-04-26026 April 1996
Proposed Improved Tech Specs
ML20100N9501996-03-0101 March 1996
Proposed TS Pages Re Drywell Leak Rate Testing Requirements
ML20100L3331996-02-27027 February 1996
Proposed Tech Specs Re Drywell Personnel Air Lock Shield Door Analyses
ML20100J5971996-02-24024 February 1996
Proposed Tech Specs,Revising Definition of Core Alteration
ML20149K2221996-02-17017 February 1996
Proposed Tech Specs,Reflecting Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6
ML20096D4651996-01-16016 January 1996
Proposed TS Requirements for Drywell Leak Rate Testing
ML20096C0591996-01-10010 January 1996
Proposed Tech Specs,Requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127
ML20095H4721995-12-20020 December 1995
Proposed Tech Specs Re Replacement of Selected Analog Leak Detection Sys Instruments W/Ge Numac Leak Detection Monitor
ML20094E6751995-11-0202 November 1995
Proposed Tech Spec,Requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operation
ML20094F2051995-11-0202 November 1995
Proposed Tech Specs for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Performing Core Alterations
ML20091R1911995-08-29029 August 1995
Proposed Tech Specs,Incorporating New Instrumentation Trip Setpoints & Allowable Values
ML20086C7281995-06-30030 June 1995
Proposed Tech Specs Re Surveillance Test Interval Extension Request
ML20084U0781995-06-0909 June 1995
Proposed Tech Specs Reflecting one-time Extension of Performance Intervals of Certain SRs
ML20084Q5351995-06-0101 June 1995
Proposed Tech Specs for Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnnp Improved TS LAR
ML20083Q1991995-05-18018 May 1995
Proposed Tech Specs for Conversion to TS Based on NUREG-1434, Improved BWR6 Ts
ML20083A6841995-05-0505 May 1995
Proposed Tech Specs Re Changes to App a TSs
ML20087H8911995-05-0101 May 1995
Proposed Tech Specs Re Incorporation of Results of Work Performed by BWROG
ML20087H9411995-04-28028 April 1995
Proposed Tech Specs Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & in Attachment 2 to Operating License
ML20087H9311995-04-28028 April 1995
Proposed Tech Specs,Proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS
ML20082C2681995-04-0303 April 1995
Proposed Tech Specs,Adding New Programmatic Requirements Governing Radiological Effluents & Relocating Procedural Details of RETS to ODCM or PCP
ML20081K3191995-03-24024 March 1995
Proposed Tech Specs Re one-time Extension of Performance Intervals for Certain TS Surveillance Requirements
1999-09-09
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E4791999-09-0909 September 1999
Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons
ML20216E4631999-09-0909 September 1999
Proposed Tech Specs Change Eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula,Since Corbicula & Zebra Mussels Have Already Been Identified & Control & Treatment Plans Are Implemented
ML20211P2871999-09-0909 September 1999
Proposed Tech Specs Pages,Increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal
ML20210M7851999-08-0404 August 1999
Proposed Tech Specs 3.9.1,incorporating Addl Option Into Required Actions When Refueling Interlocks Are Inoperable
ML20209B3391999-06-28028 June 1999
Simulator Four Yr Test Rept
ML20196A2021999-06-17017 June 1999
Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp
ML20205C6351999-03-16016 March 1999
Preliminary Rev 0 to Wps 01-43-T-801, Preliminary Weld Procedure for Perry Nuclear Power Plant Feedwater Nozzle Repair
ML20204E4971999-03-15015 March 1999
Proposed Tech Specs,Correcting Typos Found in Table 3.3.6.1-1
ML20207K1041999-03-0404 March 1999
Proposed Tech Specs Improving Licensing & Design Basis for Isolation of FW Penetrations
ML20206Q3571999-01-0606 January 1999
Proposed Tech Specs Improving Licensing & Design Basis for Isolation of Feedwater Penetrations
ML20195H5381998-11-18018 November 1998
Rev 4 to Pump & Valve Inservice Testing Program Plan
ML20155D9431998-10-27027 October 1998
Proposed Tech Specs 2.1.1.2,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by GE
ML20155D8241998-10-27027 October 1998
Proposed Tech Specs Adding Two Paragraphs to TS 5.2.2.e, Organization - Unit Staff
ML20196H5131998-10-0808 October 1998
Rev 4,Vol 1 to Inservice Exam Program for Perry Nuclear Power Plant
ML20151V4831998-09-0909 September 1998
Proposed Tech Specs Stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Check Valves Do Not Need to Be Included in Hydrostatic Program
ML20151V1111998-09-0303 September 1998
Proposed Tech Specs Permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allowing Performance of EDG 24-hour TS SR Test in Modes 1 & 2
ML20151V6861998-09-0303 September 1998
Proposed Tech Specs Increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Volume Due to Vortex Formation at Eductor Nozzles Located in Fuel Oil Storage Tank
PY-CEI-NRR-2395, Rev 5 to Perry NPP Odcm. with1998-09-0202 September 1998
Rev 5 to Perry NPP Odcm. with
ML20151S9561998-08-31031 August 1998
Proposed Tech Specs,Allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable
ML20236T7911998-07-22022 July 1998
Proposed Tech Specs Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys
ML20151P1921998-07-13013 July 1998
Proposed Tech Specs,Increasing Present +/- 1% Tolerance on Safety Mode Lift Setpoint for SRVs to +/- 3%
ML20236H8411998-06-30030 June 1998
Proposed Tech Specs,Increasing Boron Concentration in Standby Liquid Control Sys for Pnpp Cycle 8 Fuel Design & Providing Margin for Future Cycles as Required
ML20236T8451998-06-24024 June 1998
Rev 3,Change 3 to Vol 1 of Inservice Examination Program, for Pnpp
ML20216H9361998-04-14014 April 1998
Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996
ML20203G4781998-02-23023 February 1998
Maint Progress Review for Perry Nuclear Power Plant
ML20197F7871997-12-23023 December 1997
Proposed Tech Specs,Revising 3.8.1 Re AC Sources to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs
ML20217K6501997-10-22022 October 1997
Proposed Tech Specs Incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchanger
ML20217F5911997-10-0202 October 1997
Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7
ML20210T9631997-09-0808 September 1997
Proposed Tech Specs 5.2.2.e,removing Reference to NRC Policy Statement on Working Hours.Rev Allows Changes to Specific Overtime Limits & Working Hours to Be Evaluated IAW 10CFR50.59, Changes,Tests & Experiments
ML20210U8701997-09-0808 September 1997
Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp
ML20217Q4591997-08-28028 August 1997
Proposed Tech Specs 3.4.11,revising Pressure-Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90
ML20148A6871997-05-0202 May 1997
Proposed Tech Specs Re Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria
ML20148A6591997-05-0202 May 1997
Proposed Tech Specs,Revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys
ML20137S7761997-04-0909 April 1997
Proposed TS Requirements 3.9.1.1 & 3.9.2.2 Re Frequency on Refueling Equipment & one-rod-out Interlocks
ML20134D8251997-01-31031 January 1997
Proposed Tech Specs 1.1 Re definitions,3.6.1.1 Re Primary Containment - operating,3.6.1.2 Re Primary Containment Air locks,3.6.1.3 Re PCIVs,3.6.5.1 Re Drywell & 5.5 Re Programs & Manuals
ML20147B8271997-01-24024 January 1997
Rev 3 to Vol 1 of Inservice Exam Program
ML20134D8751996-10-24024 October 1996
Proposed Tech Specs 2.1.1.2,safety Limits Applying Conservatism by Increasing MCPR Safety Limit Values
ML20117E7891996-08-27027 August 1996
Proposed Tech Specs,Revising Mls Leakage Requirements & Eliminating MSIV Control Sys
ML20108A2581996-04-26026 April 1996
Proposed Improved Tech Specs
ML20100N9501996-03-0101 March 1996
Proposed TS Pages Re Drywell Leak Rate Testing Requirements
ML20100L3331996-02-27027 February 1996
Proposed Tech Specs Re Drywell Personnel Air Lock Shield Door Analyses
ML20100J5971996-02-24024 February 1996
Proposed Tech Specs,Revising Definition of Core Alteration
ML20149K2221996-02-17017 February 1996
Proposed Tech Specs,Reflecting Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6
ML20100G0161996-02-0101 February 1996
Draft Rev 0 to Pnpp NUMARC/NESP-007 Plant-Specific EAL Guidelines
ML20096D4651996-01-16016 January 1996
Proposed TS Requirements for Drywell Leak Rate Testing
ML20096C0591996-01-10010 January 1996
Proposed Tech Specs,Requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127
ML20095H4721995-12-20020 December 1995
Proposed Tech Specs Re Replacement of Selected Analog Leak Detection Sys Instruments W/Ge Numac Leak Detection Monitor
ML20108B2851995-11-22022 November 1995
Rev 5 to Offsite Dose Calculation Manual
ML20094F2051995-11-0202 November 1995
Proposed Tech Specs for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Performing Core Alterations
ML20094E6751995-11-0202 November 1995
Proposed Tech Spec,Requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operation
1999-09-09
[Table view] |
Text
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Attachm:nt 3 PY-CEl/NRR-2325L l
Page 1 of 3 I .
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l 1
PROPOSED CHANGES TO 1
TECHNICAL SPECIFICATIONS l
l I
t I ;
l j 1
i l
l
{ 9811040089 981027 i PDR ADOCK 05000440.
i P PDR
_ - m _ _ . . _ _ . _ _ . - . _ _ . _ . . _. _ ._ __. _. _ _ _ .
" ' Attachment 3
, PY-CEl/NRR-2325L
. - -- - PEgG2of3 SLs 2.0 1 l . .
2.0 SAFETY LIMITS (SLs) 1 2.1 SLs l 1
2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core j flow < 10% rateu core flow: 1 THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure a .'85 psig and core flow = 10% rated core flow:
- r. . . . . . . . _ _ _ _ _ . . . . . . . . . .-tete. - - - - - - - - - - - - - - - - - - - - - - - - - - 7 l Sly applicable for Cycle 7 cperation t
t_________.......___..__.........__..................,
1 MCPR 1 be a 1.09 for two recirculation loop operation l or 2 -He for single recirculation loop operation. i 1.11] l 2.1.1.3 Reactor vessel water level shall be greater than the top j of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL l Reactor steam dome pressure shall be 5 1325 psig.
2.2 SL Violations With any SL violation, the following action' sshall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
l 2.2.2.1 Restore compliance with all SLs: and 2.2.2.2 Insert all-insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate executive responsible for overall plant nuclear safety.
l (continued)
PERRY - UNIT 1 2.0-1 Amendment No. 91 l
t
" Attachment 3
. l PY-CEl/NRR-2325L Pege 3 of 3 Reporting Requirements 5.6
'5.6 Reporting Requirements 5.6.5 Core Operatina Limits Reoort (COLR) (continued) 4 LCO 3.3.1.1. RPS Instrumentation (SR 3.3.1.1.14):
, b. The analytical methods used to determine the core operating l
limits shall be those previously reviewed and approved by the NRC in NEDE-24011-P-A General Electric Standard l Application for Reactor Fuel. (The ap roved re' vision at the time relo analyses are performed sha 1 be identified in the COLR. l l c. The core operating limits shall be determined such that all I applicable limits (e.g. , fuel. thermal mechanical limits. I core thermal hydraulic limits. Emergency Core Cooling i Systems (ECCS) limits, nuclear limits such as SDM. transient l l analysis limits. and accident analysis limits) of the safety l analysis are met.
- d. The COLR. including any midcycle revisions or supplements. 1 shall be provided upon issuance for each reload cycle to the '
NRC.
1 5.6.6 Soecial Reoorts l l
Special Reports shall be submitted in accordance with 10 CFR 50.4 l within the time period specified for each report.
The following Special Reports shall be submitted:
- a. Violations of the requirements of the fire protection program described in the USAR which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported via the Licensee
! Event Report system.
l I + for Cyck 7. ;; apprc'/cd ir, the PRC S0fcty O/;katicr. Rcport dotcd ' l Mc'veder '7 . 1997 l
PERRY - UNIT 1 5.0-18 Amendment No. 91 l
l
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