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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop ML20036A1891993-04-30030 April 1993 Proposed TS 3/4.8, Electrical Power Sys, Paragraph 4.8.1.1.2.b,that Deals W/Automatic Load Sequence Timers on EDGs to Be Implemented During Upcoming Cycle 17 Refueling Outage ML20035G8601993-04-23023 April 1993 Proposed TS Shutdown Margin Requirements for Change in Cladding from Stainless Steel Clad Core to Zircaloy Cladding for Cycle 18 Operation ML20035A7561993-03-22022 March 1993 Proposed Tech Specs Addressing Special Test Exceptions, Electrical Power Sys Shutdown Relief Valves & Service Water Sys ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup B14391, Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing1993-03-16016 March 1993 Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria B13751, Proposed Tech Specs Re Steam Generator Overfill Protection1991-02-28028 February 1991 Proposed Tech Specs Re Steam Generator Overfill Protection ML20029B0671991-02-28028 February 1991 Proposed Tech Specs Adding Footnote to Tech Spec Table 4.3.1 Item 16, Reactor Trip Sys Breakers ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases B13555, Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-06-25025 June 1990 Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation ML20043G6311990-06-14014 June 1990 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements ML20043H0231990-06-0808 June 1990 Proposed Tech Specs Re Reactor Trip Sys Instrumentation Response Times B13520, Proposed Tech Specs Supporting Cycle 16 Operation1990-05-0909 May 1990 Proposed Tech Specs Supporting Cycle 16 Operation B13503, Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys1990-04-24024 April 1990 Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys ML20033F5551990-03-14014 March 1990 Proposed Tech Specs,Allowing Testing of Individual Rod Position Indication Sys During Power Operation B13450, Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields1990-02-16016 February 1990 Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields ML19332E4381989-11-22022 November 1989 Proposed Tech Specs Re Reactor Trip Sys Trip Setpoints & ESFAS Instrumentation B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal1989-09-29029 September 1989 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal 1999-08-24
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20046C1421993-07-0909 July 1993 Rev 12 to Response to Loss of Secondary Heat Sink ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20045H2271993-05-18018 May 1993 Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection ML20045G7991993-05-0707 May 1993 Rev 1 to Project Plan,Cyap Seismic Upgrade Program for Svc Water Sys,Feedwater Sys & Main Steam Sys Outside Containment B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop 1999-08-24
[Table view] |
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Docket No. 50-213 B14572 l
i Haddam Neck Plant-Proposed Revision to Technical Specifications Onsite Power Distribution Markup Pages
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PDR.ADOCK 05000213.
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APR 2 61990
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ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUT10N i
OPERATING LIMITIN NDITION FOR OPERATION 3.8.
A Th-following electrical busses shall be energized in the specif4 g ner with tie breakers open between redundant busses within the unit:
a.
Train A-A.C. Emergency Busses consisting of:
l 1) 4160-Volt Bus #8, and I
2) 480-Volt Busses #4 and #5.
b.
Train B-A.C. Emergency Russes consisting of:
l 1) 4160-Volt Bus #9, and j
2) 480-Volt Busses #6, #7 and #11.
c.
120-Volt A.C. Vital Bus A, energized from its associated inverter connected to D.C. Bus A, d.
120-Volt A.C. Vital Bus B, energized from its associated inverter l
connected to D.C. Bus A, i
e.
120-Volt A.C. Vital Busses C & C1, energized from its associated inverter connected to D.C. Bus B, f.
120-Volt A.C. Vital Busses D & D1 energized from its associated j
inverter connected to D.C. Bus B,
- s. 125-Volt D.C. Bus A energized from Battery Bank 1A, and 7
h.
125-Volt D.C. Busses B and BX energized from Battery Bank 18.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one of the required trains of A.C. emergency busses not fully a.
energized, reenergize the train 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
.r HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within t
the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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l HADDAM NECK 3/4 8-12 Amendment No. 125 i
APR 2 61990 l
JIJECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) b.
With one A.C. vital bus not energized from its associated inverter:
(1) return all vital busses to their normal power supply configuration 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, or (2)(a) energize the vital bus from its alternate inverter and place the reactor protection trip signal (s) associated with the inoperable bus (in abnormal configuration) in the trip condition (to meet the intent of Table 3.3-1) 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and (b) return all vital busses to their normal power supply configuration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With one D.C. bus not energized from its associated battery bank, c.
reenergize the D.C. bus from its associated battery bank within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8(f.l.1 The specified busses shall be determined energized in the required i
manner at le. t once per 7 days by verifying correct breaker alignment and indicahd' voltage on the busses.
(
i HADDAM NECK 3/4 8-13 Amendment No. 125
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ELECTRICAL POWER SYSTEMS 3/4.8.3 NSITE POWER DISTRIBUTION OPERATING LIMITING CONDITION FOR OPERATION J
l S. f. 3. I. A TOSEET A t
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3.8.3.1.2 MCC-5 shall be energized and capable of automatically obtaining power from 480 VAC Busses 5 and 6.*
APPLICABILITY: MODES 1, 2, 3, and 4.
l ACTION:
With the MCC-5 automatic transfer feature inoperable and MCC-5 energized via an onsite electrical distribution system that includes an operable diesel generator, restore the automatic transfer feature to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN-l within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
t
- The MCC-5 automatic transfer feature may be rendered IN0PERABLE for up to l
30 minutes during performance of required Cycle 18 relay testing as required per J. F. 0peka letter to U.S. Nuclear Regulatory Commission, Haddam Neck 1
Plant, Commitments to Test Motor Control Center-5, dated July 15, 1993.
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-i Docket No. 50-213 B14572 l
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Haddam Neck Plant i
Proposed Reifsion'to Technical Specifications
.i Onsite Power Distribution Retyped Pages l
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August 1993 i
s'
l ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUT10N j
OPERATING LIMITING CONDITION FOR OPERATION l
3.8.3.1.1 The following electrical busses shall be energized in the-l 1
specified manner with tie breakers open between redundant busses within the unit:
j 4
a.
Train A-A.C. Emergency Busses consisting of:
i 1) 4160-Volt Bus #8, and 2) 480-Volt Busses #4 and #5.
b.
Train B-A.C. Emergency Busses consisting of:
1) 4160-Volt Bus #9, and i
2) 480-Volt Busses #6, #7 and #11.
c.
120-Volt A.C. Vital Bus A, energized from its associated inverter connected to D.C. Bus A, i
d.
120-Volt A.C. Vital Bus B, energized from its associated inverter connected to D.C. Bus A, j
e.
120-Volt A.C. Vital Busses C & C1, energized from its associated
-i inverter connected to D.C. Bus B, f.
120-Volt A.C. Vital Busses D & D1 energized from its associated l
inverter connected to D.C. Bus B, l
t g.
125-Volt D.C. Bus A energized from Battery Bank 1A, and h,
125-Volt D.C. Busses B and BX energized from Battery Bank 18.
l APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
i a.
With one of the required trains of A.C. emergency busses not' fully energized, reenergize the train 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j HADDAM NECK 3/4 8-12 Amendment No. JJE
')
om q
-((ECTRICAL POWER SYSTEMS 3/4 8.3 ONSITE POWER DISTRIBUTION OPERATING LIMITING CONDITION FOR OPERATION ACTION (Continued) b.
With one A.C. vital bus not energized from its associated inverter:
(1) return all vital busses to their normal power supply configuration 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, or (2)(a) energize the vital bus from its alternate inverter and place the reactor protection trip signal (s) associated with the inoperable bus (in abnormal configuration) in the trip condition (to meet the intent of Table 3.3-1) 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and (b) return all vital busses to their normal power supply configuration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With one D.C. bus not energized from its associated battery bank, reenergize the D.C. bus from its associated battery bank within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.3.1.1 The specified busses shall be determined energized in the required l
manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.
HADDAM NECK 3/4 8-13 Amendment No. JJE
.0212
LLECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUT10N OPERATING LIMITING CONDITION FOR OPERATION
-i 3.8.3.1.2 MCC-5 shall be energized and capable of automatically obtaining _
power from 480 VAC Busses 5 and 6.*
j APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With the MCC-5 automatic transfer feature inoperable and MCC-5 energized via an onsite electrical distribution system that includes an operable diesel generator, restore the automatic i
transfer feature to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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- The MCC-5 automatic transfer feature may be rendered INOPERABLE for up to l
30 minutes during performance of required Cycle 18 relay testing as required per J. F. Opeka letter to U.S. Nuclear Regulatory Commission, Haddam Neck Plant, Commitments to Test Motor Control Center-5, dated July 15, 1993.
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HADDAM NECK 3/4 8-13a 0212
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