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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M5961997-03-31031 March 1997 Proposed Tech Specs,Representing Changes to TS 2.1.2,action a.1.c for LCO 3.4.1.1 & Bases for TS 2.1 ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program ML20135E8101997-03-0303 March 1997 Proposed Tech Specs 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.2 Re Isolation Actuation Instrumentation & 3/4.3.3 Re Emergency Core Cooling Sys Actuation Instrumentation ML20134M0921997-02-11011 February 1997 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20134B5511997-01-24024 January 1997 Proposed Tech Specs 3.1.3.5 Re Control Rod Scram Accumulators ML20132F1791996-12-11011 December 1996 Revised Tech Specs Re Changes to TS Bases B 3/4.3.1, Reactor Protection Sys Instrumentation, & B 3/4.3.2, Isolation Actuation Instrumentation ML20135D6851996-12-0404 December 1996 Proposed Tech Specs 3.1.3.5, CR Scram Accumulators, for Improvement & Clarifies Statement of 961025 Initial Request ML20134F3831996-10-25025 October 1996 Proposed Tech Specs 3/4.3.1,3/4.3.2 & 3/4.3.3 Re Reactor Protection Sys Instrumentation,Isolation Actuation Instrumentation & Emergency Core Cooling Sys Actuation Instrumentation ML20134F4311996-10-25025 October 1996 Proposed Tech Specs 3.1.3.5 Control Rod Scram Accumulators ML18102A2561996-07-12012 July 1996 Proposed Tech Specs Re Qualifications of Operations Manager ML18101B3831996-05-22022 May 1996 Proposed Tech Specs,Requesting Approval of Changes to QA Program 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206T8941999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9 ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20206G2281999-03-31031 March 1999 Rev 18 to ODCM for Hope Creek Generating Station ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20197H8511997-12-0808 December 1997 Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006 ML20198J6431997-10-10010 October 1997 Rev 0 to 55-WP3/F43TB3-05, Weld Procedure ML20211M6121997-10-0707 October 1997 Cycle 4 Startup Physics Testing ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20198J6541997-08-20020 August 1997 Rev 3 to 55-PQ7001-03, Procedure Qualification Record ML20198J6501997-08-20020 August 1997 Rev 5 to WP3/F43TB3-05, Welding Procedure Specification ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program 1999-09-30
[Table view] |
Text
- . _ ______ .___ - _ _ - - __ - - -- . - .. _ . - __ _ -_ __ _ . - - -_ -
4 - l
~ REACTOR PROJECTION SYSTEM INSTRtmfMTATICM SETPOINIS -
9 (continued) 4
.mmm ^ fuhCTIONAL 1mIT AlltAsABLE 33 TRIP SEIPOINT VALUE5 g 6. Main steam Line Radiation - High Hight g i 3.0 x full power background < 3.6 a full power f oo background pg 7. Drywell Pressure - High
! 1 1.68 psig i 1.88 psig C8 8. Scran Discharge Volume idater Level - High C C; .
m86 a. Float Switch zuc Elevation 110' 10.5"
=E Elevation 111' O.5"
, b. Level Transmitter / Trip Unit Elevation 110' 10.5"* Elevation 111' 4.5'a m 9. Turbine Stop Valve - Closure 0- 1 5% closed 10.
i 7% closed Turbine Control Valve fast Closure, Trip 011 Pressure - Low .
, 3 530 psig 1 465 psig i
- 11. Reactor Mode Swltch Shutdown Position M -
MA
- 12. Manual Scram M NA
'80.5" instr above - d instrument zero EL 104' 2" for Level Transmitter / Trip Unit A45 (South Header) 83.25" above .
WITIW: rare Et lav 1125* far Level Traamitter/Tria Unit ran tuaeth Me *-d prior to the pleened start of the t,t ga. :.n, ection test, with reacter power l than 22E of ' PthER, the normal full power radiati on background level t j
N setpoints may be c.~
The background rael.t on level and ascalculated rf value of the radiation 1 -
during ed trip the test. ' M
based on alther caltslations or measurements of Justed during the test program as tion. The background raJiation leve ation levels resulting from hydrogen injec-i set within 24 he,ers of -
dete: mined lated trip setpoints shall ta-injection tes ing normal radiation levels af ter coup e ~ the hydrogen ,
a 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 22% o ANAL e these functions are required to be OPERA 8tE.
i
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -
Be inthe within at next least 24HOT hours.SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CO ACTION 21 -
ACTION 22 -
within in COLD SHUTOOWN 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> within the or ne,xt 24 be hours. in et least HOT SH ACTION 23 - Be in at least STARTUP vithin 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Close the affected system isolation valves within one hour and ACTION 24 - declare the affected system inoperable.
Restore the sanual initiation function to OPERA 8LE status wit 48 and hours in COLDor SHUTDOWN be in at withinleastthe H0T following SHUTDOWN 24 hcurs. within the next 12 ACTION 25 -
Restore the manual initiation function to OPERABLE status wit 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the ACTION 26 - next hour and declare the affect.ed systee inoperable.
J Establish SECONDARY CONTAINMENT INTEG O TY w'*.h th Recirculation and Ventilation Systte (FRVS) operating within ,
one hour.
4 ACTION 27 -
i Lock the affected system isolatiott valv2s closed within one hour ACTION 28 - and declare the affected system inoperable.
Place the inoperable channel in the tripped Condition or close the affected systee affected systemir.isolationoperable. valves within one hour and declare the ACTION 29 -
place the inoperable channel in the tripped condition or establish SECONDARY CUNTAINMENT INTEGRITY with the Filtration. Rec and Ventilation System (FRYS) operating within one hour.
NOTES When handling irradiated fuel in the'se'condary containment and during C ALTERATIONS and operations with a potential for draining the reactor vesse vhen lockedany bypass turbineswitchstop is in valve the Norsis greater position. than 90% open and/or when the ke Refer to 5)ecificar, ion 3.1.5 for annlicabulinv.
M with n 24 aours pr' p or to the planned start o" the hydrogen injection tgy M
full power r ower at greater than 22% of RATED THERMAL POWER, al changed based on aon background level and associated tri nts may be the test. The backgrou lated ve.lue of the radiati expected during tion level a cisted trip setpoints may be adjusted during the test pro ments of actual radiation level either calculations or seasure-background radiation levj ros hydrogen injection. The setpoints sha)1 bg M ' thin 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br /> be determine of re estab the associated trip levels aft etion of the hydrogen injection test or normal radiation I of e 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ing reactor power levelt, below 22% of RATED THENHAL a thats functions are ranuired ta ha OpfeAAlL
- (a) t A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for re-quired surveillance without placing the trip system in the tripped condition monituting that parameter,provided at least one other OPERA 8LE channe (b) l (c) Also trips and isolates the rechanical vacuus pumps.
Also starts the Filtration, Recirculation and Ventilation System (FRVS).
j HOPE CREEK 3/4 3 16 Amendment % e
TA8tf 3.3.2-2 (Continued) ~
5 y 1501A110N ACTUATION INSTRt4ENTAIION SEIPOINIS O
- 2 TRIP TUNCTION Alt 0WA8tE 7 TRIP SE! POINT VALUE 7.
RHR SYSTIM SHUIDOW COOL 1NG MODE 150( ATION
- a. Reactor Vessel Water Level -
Low, level 3 3 12.5 inches
- b. Reactor Vessel (AHR Cut-in Permissive) Pressure - High $ 82.0 psig
- c. i 102.0 psig Manual Initiation MA NA w "See Bases figure 8 3/4 3-1.
- 1 ** Initial setpoint. Final setpoint to be determined during startup test program.
, ***These setpoints are as follows:
4'"
160*F - RWCU pipe chase room 4402 -
140*F - RWCU pump room and heat exchanger rooms 135'F - RWCU pipe chase room 4505
- 30 minute time delay. .
8815 minute time delav.
O.Tt:..- ** ':: s prior to the planned start of the hydrogen injection test, uith reactor V '
greater than IED THERMAL POE R, the normal full power radiation back iated trip setpoints me - e and assoc-during the test.* The background " ---- rbased on a calculated value of on level e 9ected evel and a rip setpoints may be adjusted during the test program based se either cale resulting from t,2;;;;;. Injection ground ras a measurements of actual radiation levels associated trip setpoi shall be determined and the i I after c 1 set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re estab ~
1 radiation levels 1
i,2; g. Injection test or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of estables ter power e ow 22% of RATED TENGAL POWER, while these functions are receired to be OPE *>etN 1 ,
l I
! INSERT l FOR TECHNICAL SPECIFICATION TABLES i l -
u 1 2.2.1-1, Reactor Protection System Instrumentation Setpoints 4 3.3.2-1, Isolation Actuation Instrumentation l 3.2.2-2, Isolation Actuation Instrumentation Setpoints
! i The hydrogen water chemistry (HWC) system shall not be !
g placed in service until reactor power reaches 20% of RATED '
3 THERMAL POWER. After reaching 20% of RATED THERMAL POWER, ;
j and prior to operating the NWC system, the normal full power 1 background radiation level and associated trip setpoints may l i be increased to levels previously measured during full power ;
i
- operation with hydrogen injection. Prior to decreasing l
- below 20% of RATED THERMAL POWER and after the NWC system !
, has been shutoff, the background level and associated l j setpoint shall be returned to the normal full power values. j J
If a power reduction event occurs so that the reactor power ;
i is below 20% of RATED THERMAL POWER without the required ;
3 setpoint change, control rod motion shall be suspended l (except for scram or other emergency actions) until the !
i necessary setpoint adjustment is made. ;
I
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iY ROSEN MINI TES" MAIN STEAM _INE MONITO' RES30NSE mse m as a vun .~
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0 0 3 10 10 14 16 17 18 22 26 30 TA 32 42 6 4 59 54 58 liYDR06EN INJECTION RATE .SCFM)
=
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General ~ Electric HWC Steam Activity: HWC/NWC 6.0 D2 M '
5.0 i r . >+# / ~
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S 2.0 , ,
' I X Duane Arnold (DA) o N V Hotch-1 (H2) 0 Nucionor (Nuc) m- g'- + Nine Mie Po!nt-1 (NMP1) 1.0 -
m-l
"" Wil ' A Miilotone (Wii)
Y Hope Creek (HC) oA soc d OPemting Point <-0.23 V SIE 0.0 -
i i i i i O.0 0.4 0.8 1.2 1.6 2.0 2.4 Feedwater Hydrogen Concentration (PPM)
Iigure I-3 NirmalIIed P',1 RM Act ivity v'. feedwater ifydrogen foncenI rat ion in Ion llWC Mini Test <.
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UNITED STATES OF A\tFRICA MJCLEAR REGULATORY C0bt4ISSION In the Matter of : Docket No. 50-352 l PillLADELPillA ELECTRIC COMPANY :
(Limerick Generating Station, : ,
Unit No. L) ;
CERTIFICATn OF SFRVICE t
I hereby certify that copies of the foregoing Application for Amendment of Facility Operating License NPF-39 in the above captioned matter were served on the following by deposit in the United States Mail, first class postage prepaid, on the 29th day of September,1988.
William T. Russell, Regional Adminir,trator U.S. Nuclear Regulatory Commission ,
Region I '
475 A11entale Road King of Prussia, PA 19406 ,
i T. J. Kenny t U.S. Nuclear Regulatory Commission !
Senior Resident Inspector {
P.O. Box 47 Sanatoga, PA 19468 l l
Thomas Gerusky, Director Bureau of Radiological Protection '
Department of Environmental Resources P.O. Dox 2063 lbrrisburg, PA 17120 l
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& No -,
uger7i J/Bradley [ l l
Attorney for 1 Philadelphia Electric Company l
1 l
1