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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 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 ML20216E4791999-09-0909 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 ML20210M7851999-08-0404 August 1999 Proposed Tech Specs 3.9.1,incorporating Addl Option Into Required Actions When Refueling Interlocks Are Inoperable ML20196A2021999-06-17017 June 1999 Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp 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 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 - 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[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
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. Attachment 2 y
~PY-CEI/NRR-1831L j CONTAINMENT SYSTEMS Page 1 of 1 cl MSIV LEAKAGE CONTROL SYSTEM
' LIMITING CONDITION FOR OPERATION
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3.6.1.4 Two independent MSIV leakage control system.(LCS)' subsystems shall be l
-OPERABLE.'
APPLICABILITY: OPERATIONAL CONDITIONS F, b , .and .
ACTION: t With one. MSIV leakage-control system subsystem inoperable, restore the
.inoper.sble subsystem to OPERA 8LE. status within 30 days or be in at least HOT SHOT 90WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following-
,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .;
SURVEILLANCE' REQUIREMENTS j 4.6.1.4 Each MSIV-leakage control-system subsystem shall be demonstrated OPERABLE:
At least once_per 31' days by_ verifying:
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~1. Blower OPERABILITY by starting the blower (s) from the control-room and operating the blower (s),for at.least 15 minutes. ,
. 2. Inboard heater OPERABILITY _by demonstrating' electrical; ,
- continuity of the. heating element circuitry by verifying' '
l the inboard heater draws 8.28 i'10% amperes per phase.
- b. During each COLD SHUTDOWN, if not performed within the previous 92-l days, by cycling each motor operated valve, including the main- ,
i steam:stop valves, through at 1 east one complete cycle'of' full, L travel.
- c. At least'once per 18 months by: ,
i-l 1. Performance of a functional, test'which includes simulated '
l- actuation of.the. subsystem throughout its' operating sequence', "
and verifying that each automatic valve actuatesito its:
! E correct position, and the blower (s) start (s)..
o
!) d$ 2. Verifying that-the blower (s) develop (s) at least the below
_ pgo- required vacuum at the rated capacity:
00
$8 a) -Inboard system,.15" H2 O at 1 100 sefs.
i' b) Outboard system, 15" H2 O at 1 200 scfm. '
OQ
@C d. By verifying the inboard flow and inboard and outboard pressure-instrumentation to be'0PERABLE by performance of'a:
4 1. CHANNEL FUNCTIONAL TEST at least once per 31- days, and-
& CHANNEL' CALIBRATION at least once per 18 months.
2.
PERRY - UNIT 5_ - -
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Attachment 3 PY-CEI/NRR-1831L Page 1 of 2 SIGNIFICAMP HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards considerations are included in the Commission's Regulations, 10 CFR 50.92, which state that the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety. 1 l
The proposed amendment has been reviewed with respect to these three factors and it has been determined that the proposed change does not involve a significant hazard because:
- 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The probability of an accident (Recirculation Line Break LOCA for which the MSIV-LCS is credited) occurring for the duration of the TS 3.6.1.4 lability of the Outboard MSIV-LCS has been Actionstatementwithunavag/
shown to be less than 1x10 reactor-year. Therefore, the probability of an accident is not significantly increased and is of a magnitude that consideration of additional compensatory measures, per ANSI /ANS 52.1-1983, is not required.
The consequences of an accident are not significantly increased in that the outboard MSIV-LCS will be available to mitigate the consequences of an accident during the period that the Inboard MSIV-LCS is unavailable.
Since the Inboard MSIV-LCS will be recovered well within the 30-day Allowable Outage Time, assurance is provided that the assumption that the Outboard MSIV-LCS is available is valid. The single failure criterion is relaxed while in the action statement (Generic Letter dated April 10, 1980).
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change to permit inoperability of the Inboard MSIV-LCS during periods of startup and power ascension to 50% RTP and during shutdown belon 50% RTP does not create the possibility of a new or different kind l of accident previously evaluated. The Inboard MSIV-LCS is only credited i during a Recirculation Line Break LOCA wherein Reactor Coolant System l i depressurization occurs. The failure of the Inboard MSIV-LCS can be
! mitigated by the Outboard MSIV-LCS.
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-- Attachment 3
^
PY-CEI/NRR-1831L Page.2 of 2
- 3. ~The proposed change does.not involve a significant reduction in a' margin-of safety.
.The response to the. Recirculation Line Break LOCA will not be significantly affected since the Outboard MSIV-LCS can be assumed to be available. In'the unlikely situation that.the Outboard MSIV-LCS'is unavailable to treat the leakage past-the MSIVs,.the leakage will be
'rcuted to the condenser. Although PNPP has not yet. performed the seismic walkdowns of the turbine line piping,-which'has been installed.and.
I supported in accordance with ANSI B31.1,~from a qualitative' standpoint it l ,is reasonably expected that the piping will withstand.the assumed l earthquake. Efforts by the Boiling Water Reactor Owners Group have shown ,
! the benefits on dose assessments in containing the Regulatory Guide 1.3-source terms in the condenser. Therefore, since 10 CFR Part 100.'is not violated, the proposed change does not involve a significant_ reduction in ,
.the margin of safety.
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