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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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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
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AttcClument 2 PY-CEI/NRR-2027L
. - Page 1 of 1 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to: I a.
$g% l An overall integrated leakage rate, except for the main steam line isolation valves #, of less than or equal to 0.75 L where L is 0.20 d kh$5 u ;
percent by weight of the primary containment aire p,,r 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,s at P,. 30g 1
{ ,
- b. aw A combined penetrations and leakage all valves, exceptrate of for less than line main steam for all to 0.60 L,i or equal g"#S j I solation A % i valves # and valves which are hydrostatically leak tested, subject to Type B and C tests when pressurize u!T 1.*4 y . '
- c. Less than or equal to 25 scf per h any one main steam line through the isolation valves when tested at P,. $0#
,e{$f d.
A combined leakage rate of less than or equal to 0.0504 L, for all m 8 % b'() i penetrations that are secondary containment bypass leakage paths when o d e o.
pressurized to the required test pressure. gV4 ;
e.
Ye0# l A combined leakage rate of less than or equal to 1 gpm times the gyew '
total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 8*5h
, I w, ,o greater than or equal to 1.10 P,.
APPLICABILITY:
jglc ,
OPERATIbNAL CONDITIONS 1, 2, AND 3, with the reactor coolant e )
system temperature greater than 200 'F.
ACTION:
i J j,5 o With: a.
The measured overall integrated rimary centainment leakage rate, l except for the main steam.line i$olation valves #, exceeding or ,ag0 0.75 L
- b. 3 egg The measured combined leakage rate for all penetrations and all a n .c a g"uo .
valves except for main steam line isolation valves # and valves which
- . 8.
are hydrostatically leak tested, subject to Type B and C tests & .
exceeding 0.60 L,, or j% $" I '
c c.
The measured leakage rate. exceeding 25 scf per h ur Jg f any one main
""agg!
Id8 steam line through the isolation valves, or gea,jj" i
- d. a j The combined leakage rate for all penetrations that are secondary ) !
containment bypass leakage paths exceeding 0.0504 L,, or i 1 i s
s Exemption to Appendix J of 10 CFR 50. J
~
PERRY - UNIT 1 3/4 6-3 Amendment No. (i, H , (q, 76 9602220049 960217 PDR p
ADOCK 05000440 #
PDR k
E qw.g. -
Att:ctunent 3
'pr-CEI/NRR-2027L Page 2 cf 1 PCIVs
. - 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
- ]
SURVEILLANCE FREQUENCY SR 3.6.1.3.9
' ------------------NOTE-------------------
Only required to be met.in MODES 1, 2, and 3.
Verify the combined leakage rate -for all -----NOTE------
secondary containment bypass leakage SR 3.0.2 is not paths is s 0.0504 L, when pressurized to applicable 2 P, . ---------------
In accordance with 10 CFR 50, Appendix J, as modified by approved exemptions SR 3.6.1.3.10 ------------------NOTE-------------------
3 Only required to be met in MODES 1, 2, and 3.
Verify leakage rate through each main ----NOTE-----
steam line'is s 25 scfh when tested at SR 3.0.2 is
~
~
a plicable Until the end of Operating cycle 6, the leakage rate through one main steam gg line is limited to s 35 scfh when 10 CFR 50 tested at Pa, as long as the total leakage rate through all four main AppendiXb steam lines is s 100 scfh. as modified by approved N exemptions (continued)
PERRY - UNIT 1 3.6-18 Amendment No. 69
.~ _ _
1 Attachment 4 i PY-CEI/NRR-2027L Page 1 of 1 SIGNIFICANT BAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment j involves no significant hazards considerations are included in the Commission's ;
Regulations, 10CFR 50.92, which state that the operation of the facility in l 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 J safety.
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. l The proposed TS change requests a relaxation of the leakage rate
, requirements for one main steam line while preserving the overall leakage rate limit for the main steam line penetrations. The proposed leakage rate I limit is well below any steam line leakage rate that is used as an accident assumption, and the proposed change would not increase the probability that a steam line rupture would occur. Therefore, the probability of an accident previously evaluated has not changed. In addition, the proposed j overall leakage rate limit is the leakage rate limit used in the accident l analysis, and that limit is not being changed by this proposal. Therefore, ;
the proposed change does not increase the consequences of an accident i previously evaluated. l
- 2. The proposed change vould not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed change increases the allovable leakage rate for one main steam line, without changing the combined leakage rate for the four main steam lines. This request does not change the method for operation of the plant.
Thus the requested change cannot create the possibility of a new or different kind of accident from any previously evaluated.
- 3. The proposed change vill not involve a significant reduction in the margin of safety.
The proposed change does not revise the overall leakage rate permitted in the present Specifications for leakage through the main steam lines. An increase in the leakage rate of any one main steam line is not considered in any accident analysis. It is the combined main steam line penetration 3 leakage rate that is assumed in the accident analysis. Thus, since this assumed leakage rate is not being revised, the proposed change does not involve a significant reduction in the margin of safety.
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