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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20213A5301987-04-20020 April 1987 Amend 4 to License NPF-58,revising Tech Specs to Require Operable RCIC Sys ML20205Q9701987-04-0101 April 1987 Amend 3 to License NPF-58,changing Max Isolation Time Allowed by Tech Specs from 50 to 20 for Operation of RCIC Sys Inboard Containment Isolation Valve 1987-04-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARPY-CEI-NRR-2427, Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations1999-09-14014 September 1999 Application for Amend to License NPF-58,deleting License Condition 2.C.10 Re Controls Over Containment Air Locks During Plant Outages & Clarifying License Condition 2.F Re Reporting Requirements of TS & EPP Violations PY-CEI-NRR-2420, Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4)1999-09-0909 September 1999 Application for Amend to License NPF-58,increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal.Proprietary SAR Encl. Proprietary SAR Withheld,Per 10CFR2.790(a)(4) PY-CEI-NRR-2406, Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl1999-09-0909 September 1999 Application for Amend to License NPF-58,eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula.Summary & Description of Change Is Encl PY-CEI-NRR-2430, Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons1999-09-0909 September 1999 Application for Amend to License NPF-58,revising Allowables 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 PY-CEI-NRR-2418, Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable1999-08-0404 August 1999 Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable PY-CEI-NRR-2398, Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp1999-06-17017 June 1999 Application for Amend to License NPF-58,changing SRs as Identified to Support Implementation of 24-month Operating Cycle at Pnpp ML20206F5971999-05-0505 May 1999 Application for Amend to License NPF-58,authorizing CEI to Possess Dl 13.74% Undivided Ownership Interest in Pnpp PY-CEI-NRR-2362, Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl1999-03-17017 March 1999 Application for Amend to License NPF-58,proposing Change in Plant USAR by Incorporating leak-off Line in RHR Sys, Which Will Significantly Reduce Collective Dose to Plant Operations Personnel.Annotated USAR Pages,Encl PY-CEI-NRR-2373, Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-11999-03-15015 March 1999 Application for Amend to License NPF-58,correcting Typos Found in TS Table 3.3.6.1-1 PY-CEI-NRR-2359, Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld1999-01-18018 January 1999 Suppl Application for Amend to License NPF-58,involving Rev of Main Steam Line Leakage Requirements & Elimination of Main Steam Isolation Valve Leakage Control Sys.Proprietary Calculations Encl.Proprietary Encls Withheld PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs1999-01-0606 January 1999 Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs PY-CEI-NRR-2325, Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld1998-10-27027 October 1998 Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld PY-CEI-NRR-2322, Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program1998-09-0909 September 1998 Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program PY-CEI-NRR-2319, Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 21998-09-0303 September 1998 Application for Amend to License NPF-58,permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allow Performance of EDG 24-hour TS SR Test in Modes 1 & 2 PY-CEI-NRR-2298, Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storag1998-09-0303 September 1998 Application for Amend to License NPF-58,increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Vol Due to Vortex Formation at Eductor Suction Nozzles Located in Fuel Oil Storage Tank PY-CEI-NRR-2300, Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable1998-08-31031 August 1998 Application for Amend to License NPF-58,allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable PY-CEI-NRR-2299, Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld1998-07-22022 July 1998 Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld ML20151P1891998-07-13013 July 1998 Application for Amend to License NPF-58,revising Safety Setpoint Requirements for Srv.Proprietary Info & Affidavit Are Contained in Attachment 5.Proprietary Info Withheld ML20236H6931998-06-30030 June 1998 Application for Amend to License NPF-58,transferring Operating Authority for Pnpp from Ceic & Centerior Svc Co to New Operating Company Named Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments,Included PY-CEI-NRR-2295, Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required1998-06-30030 June 1998 Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required PY-CEI-NRR-2245, Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs1997-12-23023 December 1997 Application for Amend to License NPF-58,revising TS 3.8.1, AC Sources - Operating, to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs PY-CEI-NRR-2230, Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers1997-10-22022 October 1997 Application for Amend to License NPF-58,incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchangers PY-CEI-NRR-2207, Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours1997-09-0808 September 1997 Application for Amend to License NPF-58,revising TS 5.2.2.e, Organization-Unit Staff, by Removing Ref to NRC Policy Statement on Working Hours PY-CEI-NRR-2206, Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.901997-08-28028 August 1997 Application for Amend to License NPF-58,revising Pressure- Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90 ML20217F5751997-07-28028 July 1997 Application for Amends to Licenses DPR-66,NPF-73 & NPF-58, Authorizing Holders to Possess Beaver Valley Power Station, Unit 1 & Authorizes Duquesne Light to Use & Operate Beaver Valley Unit 1 in Accordance W/Procedures PY-CEI-NRR-2164, Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys PY-CEI-NRR-2165, Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria1997-05-0202 May 1997 Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria PY-CEI-NRR-2155, Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks1997-04-0909 April 1997 Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks PY-CEI-NRR-2133, Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests1997-01-31031 January 1997 Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests ML20132C7601996-12-13013 December 1996 Application for Amend to License NPF-58,authorizing Transfers of Control PY-CEI-NRR-2104, Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.21996-10-24024 October 1996 Application for Amend to License NPF-58,modifying MCPR Reactor Core Safety Limit Contained in TS 2.1.1.2 ML20117E7821996-08-27027 August 1996 Application for Amend to License NPF-58,revising MSL Leakage Requirements & Eliminating MSIV Leakage Control Sys. Attachment 7 Provides Proprietary Dose Calculations. Attachment 7 Withheld PY-CEI-NRR-1999, Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process1996-04-26026 April 1996 Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process PY-CEI-NRR-2030, Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses1996-02-27027 February 1996 Application for Amend to License NPF-58 Re Drywell Personnel Air Lock Shield Door Analyses PY-CEI-NRR-2027, Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 61996-02-17017 February 1996 Application for Amend to License NPF-58,changing TS to Reflect Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6 PY-CEI-NRR-2007, Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing1996-01-16016 January 1996 Application for Amend to License NPF-58,revising TS Requirements for Drywell Leak Rate Testing PY-CEI-NRR-2013, Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 9601271996-01-10010 January 1996 Application for Amend to License NPF-58,requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127 ML20095L2181995-12-28028 December 1995 Suppl Application for License Transfer of 12.58% Ownership Interest in Addition to 17.42% Approved on 951220 PY-CEI-NRR-2004, Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc1995-11-22022 November 1995 Application for Amend to License NPF-58,revising License to Reflect License Transfer for Part of Oh Edison Co Ownership Interest in Pnpp Unit 1 to Wholly Owned Subsidiary,Oes Nuclear,Inc PY-CEI-NRR-1978, Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating1995-11-0202 November 1995 Application for Amend to License NPF-58,requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operating PY-CEI-NRR-1995, Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations1995-11-0202 November 1995 Application for Amend to License NPF-58,revising TS Requirements for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Certain Specs Related to Performing Core Alterations PY-CEI-NRR-1997, Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies1995-11-0101 November 1995 Application for Amend to License NPF-58,providing Suppl Info That Revises License to Reflect Proposed Merger of Operating Companies PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)1995-08-29029 August 1995 Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L) PY-CEI-NRR-1961, Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements1995-06-30030 June 1995 Application for Amends to Licenses NPF-58,reflecting One Time Extension of Performance Intervals for Certain TS Surveillance Requirements PY-CEI-NRR-1954, Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request1995-06-0909 June 1995 Application for Amend to License NPF-58.Amend Would Allow one-time Extension of Performance Intervals for Certain Srs. Application Supplements Original Request PY-CEI-NRR-1956, Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR1995-06-0101 June 1995 Application for Amend to License NPF-58,proposing Early Implementation of Control Rod Drive Scram Time Testing Consistent W/Requirements in Pnpp Improved TS LAR PY-CEI-NRR-1944, Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification1995-05-0505 May 1995 Suppl Application for Amend to License NPF-58,App a Tss. Suppl Addresses Minor Discrepancies & Items Needing Clarification PY-CEI-NRR-1932, Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements1995-05-0101 May 1995 Application for Amend to License NPF-58.Amend Would Incorporate Results of Work Performed by BWROG Re Elimination of Selected Response Time Testing Requirements PY-CEI-NRR-1934, Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS1995-04-28028 April 1995 Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS PY-CEI-NRR-1927, Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License1995-04-28028 April 1995 Application for Amend to License NPF-58 Re Removal of License Conditions for Tdi EDGs Specified by Paragraph 2.c & Defined in Attachment 2 to Operating License 1999-09-09
[Table view] |
Text
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/go UNITED STATES E" NUCLEAR REGULATORY COMMISSION
$ _-,; WASHINGTON, D. C. 20555 k ,/
CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. NPF-58
- 1. The Nuclear Regulatory Comission (the Comission) has found that A. The application for amendment by Cleveland Electric illuminating Company, Duquesne Light Company Ohio Edison Company , Pennsylvania PowerCompany,andToledoEdisonCompany(thelicensees) dated March 4, 1987, as supplemented on March 19, 1987, complies with the standards smended (the andAct req)uirements of the Atomic
, and the Conrnission's rulesEnergy Act of 1954, and regulations set as i
forth in 10 CFR Chapter It B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 4
Comission;
, C. Thereisreasonableassurance(1)thattheactiviticsauthorizedby this amendment can be conducted without endangering the health and
, safety of the public, and (ii) that such activities will be conducted
! in compliance with the Comission's regulations; 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 amendment is in accordance with 10 CFR Part 51
- of the Comission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications 3 as indicated in the attachment to this license amendment, and paragraph 2.C.(2) 1 of Facility Operating License No. NPF-58 is hereby amended to read as follows:
Technical Specifications l
i The Technical Specifications contained in Appendix A and the Environ-2 mental Protection Plan contained in Appendix B, as revised through Amendment No. 3 are hereby incorporated into this license. Cleveland Electric Illuminating Company shall cperate the facility in accordance
, with the Technical Specifications and the Environmental Protection Plan.
l 0704060140 070401 PDR ADOCK 05000440 P PDR
2-
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Chances to the Technical '
Specifications Date of Issuance: April 1, 1987 aa q///87
,;..c , a (h/Q/87 l
a//87j/y}/07W..t,.,e 37
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[
Walter R. Butler, Director BWR Pro.iect Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications l Date of Issuance: April 1, 1987 i
l
ATTACPMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Repia e the following pages of the Appendix "A" Technical Specifications with l the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleafpage(s)are provided to maintain document completeness.*
Remove Insen 3/4 6-31 3/4 6-31 3/4 6-32 3/4 6-32*
3/4 8-13 3/4 8-13*
3/4 8-14 3/4 8-14 3/4 8-17 3/4 8-17*
3/4 8-18 3/4 8-18 3/4 8-19 3/4 8-19 3/4 8-20 3/4 8-20*
A ~; ..
~.
- a. CONTAINMENT AUTOMATIC ISOLATION VALVES (Continued) a E Valve Penetration Valve Maximum Secondary Test i Number Number Group (c) Isolation Time Containment Pressure n
(Seconds) Bypass Path (Psig) e (Yes/No) 5*
" 1E21-F011 P105 17 20* No (b) 1E21-F012 P105 2 180* No (b) ,
1E22-F004 P410 16 27 No(h) 11.31 1E22-F012 P409 16 5 No(h) 11.31 1E22-F023 P409 1 180* No(h) 11.31 1E32-F001A P124 10 20 No 11.31 IE32-F001E P416 10 20 No 11.31
'1E32-F001J P122 10 20 No 11.31 1E32-F001N P415 10 20 No 11.31 i 4* IE51-F031(I) i) P101 9 30 No (b)
P422 9 20 T 'IE51-F063((I)'
1E51-F064 P422 9 10 No(h)
No 11.31l 11.31 i O P422 9 15* No 11.31
'1E51-F076((I) 1E51-F077 i) P106, P107 P115, P429 9 22.5* No 11.31 1G33-F001 P131 7 15 Yes 11.31 IG33-F004 P131 7 15 Yes 11.31
-1G33-F028 P424 7 15 Yes 11.31 IG33-F034 P424 7 15 Ye 11.31 1G33-F039 P132 7 15 No h) 11.31 1G33-F040 P132 7 15 No 11.31
[ 1G33-F053 P419 7 15 Yes 11.31
, g 1G33-F054 P419 7 15 Yes 11.31 R
a '
. .E u ;
j e e
- a. CONTAINMENT AUTOMATIC ISOLATION VALVES (Centinu:d)
A
- E Valve Penetration Maximum Secondary Test
-< Number Number Valve Group (c) Isolation Time Containment Pressure
' Bypass Path (Psig)
- (Seconds) ,
3 (Yes/No)
U IG41-F100 P203 1 30 Yes 11.31 H 1G41-F140 P301 1 30 Yes 11.31 4
1G41-F145 P301 1 30 Yes 11.31 1G50-F272 P420 1 20* Yes 11.31 IG50-F277 P420 1 20* Yes 11.31 IG61-F075 P417 1 22 Yes 11.31 1G61-F080 P417 1 22 Yes 11.31 1G61-F165 P418 1 22 Yes 11.31 1G61-F170 P418 1 22 Yes 11.31 IM14-F040 V313 8 4 Yes 11.31
' w IM14-F045(j) V313 8 4 Yes 11.31 '
) IM14-F085(j) V314 8 4 Yes 11.31
. IM14-F090 V314 8 4 Yes 11.31 4
N IM14-F190 V313 8 4 Yes 11.31 IM14-F200 V314 8 4 Yes 11.31 IM14-F195 V313 8 4 Yes 11.31 1M14-F205 V314 8 4 Yes 11.31 IM17-F015 P114 5 5 Yes 11'.31 1M17-F025 P208 5 5 Yes 11.31 1M17-F035 P428 5 5 Yes 11.31 1M17-F045 P436 5 5- Yes 11.31 IM51-F090 P302 2 30* No 11.31 IM51-F110 P302 2 30* No 11.31 1P11-F060 P108 1 30 Yes 11.31 IP11-F080 Pill 1 30 Yes 11.31 IP11-F090 Pill 1 30 Yes 11.31 IP22-F010 P309 1 22 Yes 11.31 1P43-F055 P310 2 30 Yes 11.31 1P43-F140 P311 2 30 Yes 11.31 1P43-F215 P311 2 30 Yes 11.31 t
S .
$ f Q- ., - ___ _ _ _ _ _ __ _ _ _ _ __
L .
ELECTRICAL POWER SYSTEMS t
SURVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 92 dtys anc! within 7 days after a battery discharge s
with battery terminal voltage below 110 volts, or battery overcharge with battery terminal voltage above 145 volts, by verifying that:
- 1. The parameters in Table 4.8.2.1-1 meet the Category B limits,
- 2. There is no visible corrosion at either terminals or connectors, l or the connection resistance of each cell-to-cell and terminal '
connection is less than or equal to 50 x 10 8 ohms for Div 1 and Div 2 batteries and 100 x 10 s ohms for the Div 3 battery.
- 3. The average electrolyte temperature of 10 connected cells is above 72*F.
- c. At least once per 18 months by verifying that:
- 1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration,
- 2. The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material,
- 3. The resistance of each cell-to-cell and terminal connection is less than or equal to 50 x 10 s ohms for Div 1 and Div 2 batteries and 100 x 10 s ohms for the Div 3 battery.
- 4. The battery chargers 1R42-S006, -5008, OR42-5007, and -S009 will each supply at least 400 amperes at a minimum of 125 volts for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
- 5. The battery chargers 1E22-5006 and OR42-5011 will each supply at least 50 amperes at a minimum of 125 volts for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- d. At least once per 18 months, during shutdown, by verifying that either:
- 1. The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design duty cycle when the battery is subjected to a battery service test, or
- 2. The battery capacity is adequate to supply a dummy load of the following profile while maintaining the battery terminal voltage greater than or equal to 105 volts.
O PERRY - UNIT 1 3/4 8-13
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a) Division 1
> 604 amps for the first 60 seconds i 127 amps for the next 9 minutes I 380 amps for the next 1 minute
[127ampsforthenext108 minutes 1 326 amps for the last 60 seconds b) Division 2 1 395 amps for the first 60 seconds l 1 119 amps for the next 9 minutes 1 372 amps for the next 1 minute 1 119 amps for the next 108 minutes 1 316 amps for the last 60 seconds c) Division 3
> 95 amps for the first 60 seconds
[16ampsforthelast119 minutes '
- e. At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% cf the anufacturer's rating when subjected to a performance discharge test. At this once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test.
- f. At least once per 18 months, during shutdown, performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.
l Amendment No. 3 i PERRY - UNIT 1 3/4 8-14
' i ELECTRICAL POWER SYSTEMS i l
3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS l DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION l l
3.8.3.1 The following power distribution system divisions shall be energized:
- a. A.C. power distribution:
- 1. Division 1, consisting of: -
a) 4160 volt A.C. bus EH11.
b) 480 volt A.C. busses EF-1-A and EF-1-B.
c) 480 volt A.C. MCCs EF-1-A-07, EF-1-A-08, EF-1-A-09, EF-1-A-12, EF-1-B-07, EF-1-B-08, EF-1-B-09, and EF-1-B-10/EF-1-D-10.**
d) 120 volt A.C. distribution panels EB-1-Al and EK-1-Al in 480 volt MCCs EF-1-B-07 and EF-1-A-07.
e) 120 volt A.C. bus EV-1-A energized from inverter 1R14-5012 connected to D.C. bus ED-1-A-06.*
- 2. Division 2, consisting of:
a) 4160 volt A.C. bus EH12. d b) 480 volt A.C. busses EF-1-C and EF-1-D.
c) 480 volt A.C. MCCs EF-1-C-07, EF-1-C-08, EF-1-C-09, EF-1-C-12, EF-1-D-07, EF-1-D-08, and EF-1-D-09. 1 d) 120 volt A.C. distribution panels EB-1-B1 and EK-1-B1 in ;
480 volt MCCs EF-1-D-07 and EF-1-C-07.
e) 120 volt A.C. bus EV-1-B energized from inverter 1R14-S013 connected to D.C. bus ED-1-B-08.*
- 3. Division 3, consisting of:
a) 4160 volt A.C. bus EH13. .
b) 480 volt A.C. MCCs EF-1-E-1 and EF-1-E-2.
c) 120 volt A.C. distribution panel EK-1-C1 in 480 volt MCCs EF-1-E-1.
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- b. D.C. power distribution:
- 1. Division 1, consisting of 125. volt D.C. distribution panels ED-1-A-06 and MCC E0-1-A-09.
- 0ne inverter may be disconnected from its D.C. source for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the purpose of performing an equalizing charge on the associated battery l bank provided (1) its AC bus remains OPERABLE and energized, and the AC bus i associated with the other battery bank is OPERABLE and energized. l
- 480 volt MCC EF-1-B-10/EF-1-D-10 is normally energized from Division 1.
Division 2 provides an alternate power source.
PERRY - UNIT 1 3/4 8-17
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ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) 4 ,
- 2. Division 2, consisting of 125 volt D.C. distribution panels 1 ED-1-B-06 and ED-1-B-08.
- 3. Division 3, consisting of 125 volt D.C. distribution panel 1R42-5037.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
- a. For A.C. power distribution:
- 1. With either Division 1 or Division 2 of the above required A.C.
distribution system not energized, re-energize the division within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN 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 />. .
- 2. With Division 3 of the above required A.C. distribution system not energized, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.1. -
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- b. For D.C. power distribution:
- 1. With either Division 1 or Division 2 of the above required D.C.
distribution system not energized, re-energize the division
' within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN 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 />.
- 2. With Division 3 of the above required D.C. distribution system not energized, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.1. i i
SURVEILLANCE REQUIREMENTS 4.8.3.1 Each of the above required power distribution system divisions shall be determined energized at least once per 7 days by verifying voltage and correct breaker alignment on the busses /MCCs/ panels.
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- t PERRY - UNIT 1- 3/4 8-18 . Amendment No. 3 4
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. , . - , - , ,- - , - - - - , - - - - - - - - - . - - - + . - - - . - - - . . .
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ELECTRICAL POWER SYSTEMS DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following power distribution system divisions shall be energized:
- a. For A.C. power distribution, Division 1 or Division 2, and when the HPCS system is required to be OPERABLE, Division 3, with:
- 1. Division 1 consisting of: -
l a) 4160 volt A.C. bus EH11.
b) 480 volt A.C. busses EF-1-A and EF-1-B.
c) 480 volt A.C. MCCs EF-1-A-07, EF-1-A-08, EF-1-A-09, ,
EF-1-A-12, EF-1-B-07, EF-1-B-08, EF-1-B-09, and j EF-1-B-10/EF-1-D-10.*
d) 120 volt A.C. distribution panels EB-1-Al and EK-1-Al in 480 volt MCCs EF-1-B-07 and EF-1-A-07.
e) 120 volt A.C. bus EV-1-A energized from inverter 1R14-5012 connected to D.C. bus ED-1-A-06, or energized from A.C. bus EF-1-B-07.
Division 2 consisting of:
2.
a) 4160 volt A.C. bus EH12.
' b) 480 volt A.C. busses EF-1-C and EF-1-D.
c) 480 volt A.C. MCCs EF-1-C-07, EF-1-C-08, EF-1-C-09, EF-1-C-12, EF-1-D-07, EF-1-D-08, and EF-1-D-09, d) 120 volt A.C. distribution panels EB-1-B1 and EK-1-B1 in j
480 volt MCCs EF-1-D-07 and EF-1-C-07.
e) 120 volt A.C. bus EV-1-B energized from inverter 1R14-S013 l connected to D.C. bus ED-1-B-08 or energized from A.C.
bus EF-1-D-09.
- 3. Division 3 consisting of: ,
a) 4160 volt A.C. bus EH13.
b) 480 volt A.C. MCCs EF-1-E-1 and EF-1-E-2.
c) 120 volt A.C. distribution panel EK-1-C1 in 480 volt MCC EF-1-E-1.
- b. For D.C. power distribution, Division 1 or Division 2, and when the HPCS system is required to be OPERABLE, Division 3, with:
- 1. Division 1 consisting of 125 volt D.C. distribution panels ED-1-A-06 and MCC ED-1-A-09.
! 2. Division 2 consisting of 125 volt D.C. distribution panels ED-1-B-06 and ED-1-B-08.
i
- 480 volt MCC EF-1-B-10/EF-1-D-10 is normally energized from Division 1. .
- Division 2 provides an alternate power source.
PERRY - UNIT 1 3/4 8-19 Amendment No. 3
7f '. _ .
ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) ,
- 3. Division 3 consisting of 125 volt D.C. distribution panel IR42-S037.
APPLICABILITY: OPERATIONAL CONDITIONS 4, 5 and *.
ACTION:
- a. For A.C. power distribution:
- 1. With less than Division 1 and/or Division 2 of the above required A.C. distribution system energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the Fuel Handling Building and primary containment and operations with a potential for draining the reactor vessel.
- 2. With Division 3 of the above required A.C. distribution system not energized, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.2 and 3.5.3.
For D.C. power distribution:
b.
- 1. With less than Division 1 and/or Division 2 of the above required D.C. distribution' system energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the Fuel Handling Building and primary containment and operations with a potential for draining the reactor vessel.
- 2. With Division 3 of the above required D.C. distribution system not energized, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.2 and 3.5.3.
- c. The provisions of Specification 3.0.3 are not app'licable.
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! SURVEILLANCE RECUIREMENTS i - l 4.8.3.2 At least the above required power distribution system divisions shall be determined energized at least once per 7 days by verifying voltage and correct breaker alignment on the busses /MCCs/ panels.
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- When handling irradiated fuel in the Fuel' Handling Building or primary
. containment.
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PERRY - UNIT 1 3/4 8-20 i . . . _ . _ _- _ . _ . _ , _ _ _ . _ , - . _ - ._ _ __ , _ _ _ ___ . - - _ _ - .