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Category:TECHNICAL SPECIFICATIONS
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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 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 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 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 ML20210U8701997-09-0808 September 1997 Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp 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 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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c -
CONTAINMENT SYSTEMS MSIV LEAKAGE CONTROL SYSTEM MITING CONDITION FOR ?.'/ERATION
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3.6. 4 Two independent MSIV leakage control system (LCS) subsystems s 11 be OPERA E.
APPLICAB 4.ITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one MSIV akage control system subsystem inoperable, re ore the inoperable subs tem to OPERABLE status within 30 days or b in at least HOT SHUTDOWN within t 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 wit n the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. i SURVEILLANCE REQUIREM TS x <
4.6.1.4 Each MSIV leakag controlsystemsubsyste!shallbedemonstrated OPERABLE:
- a. At least once per 31 ays by verify g:
- 1. Blower OPERABILITY y start g the blower (s) from the control room and operating t e blo r(s) for at least 15 minutes.
- 2. Inboard heater OPERABIL Y by demonstrating electrical continuity of the hea n element circuitry by verifying the inboard heater d ws 28 1 10% amperes per phase.
- b. During each COLD SHUTD N, if not erformed within the previous 92 days, by cycling eacty motor operate valve, including the main steam stop valves, trough at least o .e complete cycle of full travel,
- c. At least once r 18 months by:
- 1. Perfor nce of a functional test which cludes simulated actua on of the subsystem throughout its perating sequence, i and erifying that each automatic valve ac ates to its co ect position, and the blower (s) start (s).
- 2. erifying that the blower (s) develop (s) at leas the below required vacuum at the rated capacity:
a) Inboard system, 15" H2 O at 1 100 scfm.
b) Outboard system, 15" H2 O at 1 200 scfm.
- d. By verifying the inboard flow and inboard and outboard pressur instrumentation to be OPERABLE by performance of a:
- 1. CHANNEL FUNCTIONAL TEST at least once per 31 days, and ;
- 2. CHANNEL CALIBRATION at least once per 18 months. 1 PERRY - UNIT 1 3/4 6-8 g92404jO B7092e I p ADOCK 0500044o PDR
' CONT 5INMENTSYSTEMS BASES M .4 MSIV LEAKAGE CONTROL SYSTEM Calc W resulting from the maximum leakage nce for the main steam line isolatio ives in the postulated LOCA ions would be a small )
fraction of the 10 CFR 100 guide nes, provi e main steam line system from the isolation valves up to and ing the turbine condenser remains intact. Operating experiences dicate degradation has occasionally I occurred in the leak ti tee 3s of the MSIV's such the specified leakage requirements have always been maintained continuous . e requirement for ;
the leaka rol system will reduce the untreated leakage fr MSIV's l whe ation of the primary system and containment is required.
3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be ma'intained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual j inspection in conjunction with Type A leakage tests is sufficient to demonstrate 1 this capability.
3/4.6.1.6 CONTAINMENT INTERNAL PRESSURE The limitations on primary containment to secondary containment differen-tial pressure ensure that the primary containment peak pressure of 11.31 psig does not exceed the design pressure of 15.0 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of +0.8 psid. The limit of -0.1 to +1.0 psid for initial positive primary containment to secondary containment pressure will limit the primary containment pressure to 11.31 psid which is less than the design pres-sure and is consistent with the safety analysis.
3/4.6.1.7 CONTAINMENT [VERAGE AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment peak air temperature does not excee~d the design temperature of 185*F during LOCA conditions and is consistent with the safety analysis.
3/4.6.1.8 DRYWELL AND CONTAINMENT PURGE SYSTEM The use of the drywell and cc stainment purge lines is restricted to the 42-inch outboard and 18-inch purra supply and exhaust isolation valves. These valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines <>f 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations. The term sealed closed as used in this context means that the valve is secured in its closed position l
by deactivating the valve motor operator, and does not pertain to injecting seal l water between the isolation valves by a seal water system.
l l
PERRY - UNIT 1 B 3/4 6-2
(
j- CONTAINMENT SYSTEMS
! PRIMARY CONTAINMENT LEAKAGE i LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of less than or equal to 0.75 L,,
0.20 percent by weight of the primary containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 11.31 psig.
- b. for all A combined leakage penetrations rate of except and all valves, less than for or equal main to 0.60 steam line L, isolation valves and valves which are hydrostatically leak tested per Table 3.6.4-1, subject to Type B and C tests when pressurized to P,, 11.31 psig.
c.
/00 a//
Less than or equal to FJ scf per hour for =y := main steam lines ^
through tha isolation valves when tested at P,, 11.31 psig.
- d. A combined leakage rate of less than or equal to 0.0504 L for all penetrations shown in Table 3.6.4-1 of Specification 3.6.4 as secondary containment bypass leakage paths when pressurized in accorcance with Table 3.6.4-1.
- e. A combined leakage rate of less than or equal to 1 gpm times the total number-of containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, when tested at 1.10 P,, 12.44 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.
ACTION:
With:
- a. The measured overall integrated primary containment leakage rate exceeding 0.75 L,, or
- b. The measured combined leakage rate for all penetrations and all valves except for main steam line isolation valves and valves which are hydrostatically leak tested per Table 3.6.4-1, subject to Type B and C tests exceeding 0.60 L,, or The measured leakage rate exceeding too,26'scf per hour fora/any/
- c. en:
main steam lineSthrough the isolation valves, or A
- d. The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths exceeding 0.0504 L,, or
- e. The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which pene-trate the primary containment exceeding 1 gpm times the total number of such valves:
"See Special Test Exception 3.10.1.
PERRY - UNIT 1 3/4 6-3
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) restore:
- a. The overall integrated leakage rate (s) to less than or equal to 0.75 L,, and
- b. The combined leakage rate for all penetrations and all valves except for main steam line isolation valves and valves which are hydrostati-cally leak tested per Table 3.6.4-1, subject to Type B and C tests to less than or equal to 0.60 L,, and
/00 g1
- c. The leakage rate to less than JEscf per hour for ry/f= main steam linesthrough the isolation valves, and A
- d. The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths to less than or equal to 0.0504 L,, and
- e. The combined leakage rate for all containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200 F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the cri-teria specified in Appendix J of 10 CFR Part 50 using the methods and provi-sions of ANSI N45.4-1972 and BN-TOP-1; test results shall also be reported '
based on the Mass Point Methodology described in ANSI /ANS N56.8-1981:
- a. Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 + 10 month intervals during shutdown at P ,
11.31 psig during each 10 year service period. Thethirdteltof each set shall be conducted during the shutdown for the 10 year plant inservice inspection.
- b. If any periodic Type A test fails to meet 0.75 L , the test schedule I forsubsequentTypeAtestsshallbereviewedan8approvedbythe Commission. If two consecutive Type A tests fail to meet 0.75 L Type A test shall be performed at least every 18 months until tw8, a consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.
- c. The accuracy of each Type A test shall be verified by a supplemental test which: v- !n 10),<_.'
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