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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 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 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 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 ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup 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 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 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 ML20245J1451989-08-0404 August 1989 Proposed Tech Specs Re Containment Air Recirculation Sys, Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys ML20248D7711989-08-0202 August 1989 Proposed Tech Spec 3/4.5.1 Revising ECCS to Reflect Component Configurations Following 1989 Refueling Outage Mods to ECCS to Resolve Single Failure Concerns Identified on Three Separate Occassions B13327, Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests1989-08-0101 August 1989 Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests ML20248B2771989-07-31031 July 1989 Proposed Tech Specs Re Fire Detection & Spray &/Or Sprinkler Sys B13284, Proposed Tech Spec 3.6 Re ECCS1989-07-31031 July 1989 Proposed Tech Spec 3.6 Re ECCS B13314, Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys1989-07-28028 July 1989 Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage1989-07-28028 July 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage B13292, Proposed Tech Specs,Supporting Cycle 161989-07-28028 July 1989 Proposed Tech Specs,Supporting Cycle 16 B13181, Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS1989-06-30030 June 1989 Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes1989-06-29029 June 1989 Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes B13269, Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation1989-06-23023 June 1989 Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation ML20245D2281989-06-15015 June 1989 Proposed Tech Specs Re Cycle 15 Operation Coastdown Analysis & Operation A07433, Proposed Tech Specs Re Leakage Detection Sys1989-05-30030 May 1989 Proposed Tech Specs Re Leakage Detection Sys B13256, Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual1989-05-25025 May 1989 Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual B13169, Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs1989-04-30030 April 1989 Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs B13208, Proposed Tech Specs Supporting Operation of Cycle 151989-04-30030 April 1989 Proposed Tech Specs Supporting Operation of Cycle 15 ML20245F2581989-04-25025 April 1989 Proposed Tech Specs Re Administrative Controls in High Radiation Area B13201, Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power1989-03-31031 March 1989 Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power B13098, Proposed Tech Specs Re Administrative Controls & Organizational Charts1989-03-13013 March 1989 Proposed Tech Specs Re Administrative Controls & Organizational Charts B13151, Proposed Tech Specs 3/4.1, Reactivity Control Sys1989-03-0606 March 1989 Proposed Tech Specs 3/4.1, Reactivity Control Sys B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-371989-03-0101 March 1989 Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 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 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 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 ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification 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 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 ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup 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 ML20127E2901993-01-11011 January 1993 Rev 43 to Corporate Organization for Nuclear Incidents (Coni) Procedure Coni 1.02,page 7.2-2 of 2,Figure 7.2, Cero Staff-Managers Annual On-Call Schedule B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20217A6311990-11-14014 November 1990 Rev 0 to Haddam Neck Plant Reactor Containment Bldg Integrated Leak Rate Test ML20058H0611990-10-31031 October 1990 Core Xvi Startup Physics Test Rept 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 1999-08-24
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Docket No. 50-213 B12544 Attachment 1 Haddam Neck Plant Proposed Revision to Technical Specifications June,1937
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8706090224 870601 PDR ADOCK 05000213 P PDR
3.6 CORE COOLING SYSTEMS
- Applicability: Applies. to the operating status of the core cooling systems.
Objective: To define those limiting conditions for operation that are necessary to insure operability of the core cooling system.
Specification: A) The reactor shall not be critical unless the following conditions are met:
- 1) Pumps All of the pumps associated with at least one of the two trains of emergency core cooling equipment must be operable. The pumps associated with each train of emergency core cooling equipment are the following:
- a. One high pressure safety injection pump rated at 1750 gpm at a head of 2250 feet.
- b. One charging pump rated at 360 gpm at a pressure of 2300 psig,
- c. One low pressure safety injection (core deluge) pump rated at 5500 gpm at a head of 590 feet.
- d. One residual heat removal (RHR) pump rated at 2200 gpm at a total head of 300 feet.
- 2) At least one of two residual heat exchangers operable.
- 3) System valves and interlocks required for proper operation of core cooling systems operable.
B) The following valves and their operators will be positioned and verified as stated below:
- 1) Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> VALVE NO. LOCATION ACTION RH-FCV-602 RHR heat Valve locked in closed exchanger position, Air supply bypass line isolated whenever reactor critical and i
coolant temperature is above 3500F. l RH-FCV-796 RHR heat Valve blocked in the l exchanger throttled position, Air discharge supply isolated when-line ever reactor critical and coolant temperature 3-10 is above 3500F. l l
k
VALVE NO. LOCATION ACTION RH-MOV-22 Containment Valve locked in open Sump position, circuit Suction breaker locked open l during post-LOCA long-term cooling phase.
SI-MOV-24 RWST line Valve locked in open position, circuit breaker locked open whenever reactor coolant temperature is above 3500F.
SI-FCV-875 HPSI mini- Valve blocked and locked flow line in open position whenever reactor coolant temperature is above 3500F.
RH-MOV-874 RHR recirc- Valve locked in closed ulation position and circuit breaker locked open whenever reactor is critical and reactor coolant temperature is above 350oF.*
SI-MOV-854A HPSI Pump Valve locked in open Suction Line position whenever reactor coolant temperature is above 3500F.
SI-MOV-854B HPSI Pump Valve locked in open Suction Line position whenever i
reactor coolant temperature is above 3500F.
~ SI-MOV-901 RHR/HPSI Valve locked in closed Crosstle position whenever reactor coolant temperature is above 3500F.
SI-MOV-902 RHR/HPSI Valve locked in closed Crosstle position whenever reactor coolant temperature is above 3500F.
3-10a
- 2) Prior to startup from cold shutdown (Mode' 5)
VALVE NO. LOCATION ACTION SI-V-907 HPSI loop 1 Valve blocked and locked injection line in throttled position.
SI-V-903 HPSI loop 2 Valve blocked and locked <
injection line in throttled position.
SI-V-906 HPSI loop 3 Valve blocked and locked injection line in throttled position.
SI-V-905 HPSI loop 4 Valve blocked and locked injection line in throttled position.
SI-MOV-873 Core deluge Valve is locked open line and electrically dis-connected. ,
C. The following actions shall be taken to disable the High _ Pressure Safety injection Pumps whenever the RCS temperature is below 3400F and the RCS is not vented by a minimum opening of three (3) inches (nominal diameter) or its equivalent.
- 1. De-energize the HPSI pumps by racking out the breakers and locking the cabinets.
- 2. Close and lock the HPSI pump discharge valves (SI-V-855A & B).
D. The following actions shall be taken to disable one centrifugal charging pump .
whenever the RCS temperature is below 3400F and the RCS is not vented by a minimum opening of three (3) inches (nominal diameter) or its equivalent.
- 1. Place the control switch in the trip pullout position. ;
- 2. Red tag the switch "DO NOT OPERATE."
BASIS This specification assures that adequate emergency core cooling capacity is +
available whenever the reactor is critical. Based on the loss of coolant accident l analysis, melting of the cladding is prevented with only one high pressure safety injection pump and one low pressure safety injection (core deluge) pump in operation. Additionally, during the post-LOCA recirculation phase, sufficient cooling exists with only one charging, one HPSI, and one RHR available. Each of the two trains of emergency core cooling equipment includes these three pumps.
- With the pumps associated with both trains of emergency core cooling equipment operable, 3-10b i
i
substantial margin exists whenever normal power supplies or both diesel generators are available. With only one diesel generator operating and the pumps associated with that diesel operable as required in Item (2) of Specification 3.12, the high pressure safety injection pump and the low pressure safety injection pump would be started automatically. When the safety injection pumps are operating on off-site power, the charging pump would be started automatically. The RHR and charging pumps would be available for manual start for long-term recirculation cooling.
As described in Reference 3, the RCS OPS, in conjunction with administrative controls, prevents exceeding the temperature and pressure limits in Specification 3.4 while RCS temperature is under 3400F or the RCS is not vented. Part C establishing limiting condition for operation regarding the disabling of the HPSI pumps to further assure that a pressure transient is not initiated. Part D establishes requirements regarding the disabling of a charging pump to assure that a pressure transient is not initiated while retaining the flexibility to establish, under strict administrative controls, a redundant emergency boration path should such action be necessary.
FCV-796 is required to be throttled open within the range specified in and for the reasons sited within References (6) and (7). That throttled position has been determined by separate analyses to insure acceptable core performance during post-LOCA recirculation.
In order to use the HPSI pumps to provide high pressure recirculation following a small break loss of coolant accident (LOCA) coincident with a single active failure, the following modifications to the emergency core cooling system have been made.
A piping crosstic between each HPSI pump suction and the RHR pump discharge has been installed. Two valves, SI-MOV-901 and SI-MOV-902 have been installed in this crosstie. The two manual HPSI pump suction valves have been replaced with motor-operated valves, SI-MOV-354A and B, to prevent contaminated water from entering the RWST when using the HPSI pumps to provide flow to the core during recirculation. These values will not be energized until 1939 and no credit will be taken for their use until this time and they will be locked in their safe position.
The manual core deluge isolation valve has been replaced with a de-energized motor-operated valve, SI-MOV-373. This valve will be locked open to ensure that adequate flow is available to the core deluge system.
REFERENCE:
(3) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),
dated May 22,1973.
(4) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),
dated May 24, 1973.
(5) D.C. Switzer (CYAPCO) letter to A. Schwencer (NRC),
dated September 7,1977.
(6) E.3. Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated December 17,1986.
(7) E.J. Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated December 19, 1936.
3-10c
F) Periodic leakage testing of each ECCS check valve listed in Table 4.3.1 shall be accomplished prior to entering operational mode 1:
- 1) Af ter every time the plant is placed in the cold shutdown condition for refueling.
- 2) Af ter every time the plant has been placed in the cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months.
- 3) Prior to returning the valve to service af ter maintenance, repair, or replacement work is performed.
Leakage may be measured indirectly using pressure indicators, if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating compliance with the leakage criteria of section 3.14.A.6. The minimum differential pressure across these check valves during these leakage tests shall not be less than 150 psid.
Table 4.3.1 - ECCS Check Valve SI-CV-862A SI-CV-862B SI-CV-862C SI-CV-862D SI-CV-872A SI-CV-872B G) The correct position of each ECCS throttle valve listed below shall be verified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
ECCS Throttle Valves Valve Number Valve Number SI-V-905 SI-V-907 SI-V-906 SI-V-908 RH-FCV-796 H) A flow balance test shall be performed, during Mode 5 or 6, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics, to verify that:
- 1) For the High Pressure Safety injection pump injection lines, with a single pump running and two lines isolated, the flow rate through each line is equal to 1000 + 100 gpm.
i 4-4a
- 2) For RHR pump discharge lines, with a single pump running, the.
flow rate through the discharge line is equal to 15003,280 gpm.
Basis: The core cooling systems are the principal plant safeguard. They provide the means to insert negative reactivity and limit core damage in the event of a loss-of-coolant incident.
Pre-operational performance tests of the components are performed in the manufacturer's shop. An initial system flow test demonstrates proper dynamic functioning of the system. Thereaf ter, periodic tests demonstrate that all components are functioning properly.
Surveillance requirements for throttle valve position and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.
In order to assure that a pressure transient occurring during the testing of the HPSI pumps will not exceed the pressure and temperature limits of specification 3.4, there must be appropriate relief paths available; this is provided for in specification 4.3.A.4.
The separation of emergency power systems and associated core cooling equipment into two independent groupings permits complete function testing of the individual systems and equipment.
The containment spray water is provided,if required, by the low pressure safety injection pumps, which are also part of the core deluge system. It is not desirable to test the valve at monthly intervals since it requires closure of a -
manual valve in the spray header. This valve must be closed to prevent initiation of spray when the moter-operated spray valve is open since the residual heat removal system will always be pressurized. Closure of the manual valve is not desirable at power and, therefore, dictates that the motor-operated spray valve be tested at refueling intervals only.
The surveillance in Specification E) assures that the limiting conditions for operation required for low temperature overpressurization protection have been met.
i The surveillance in Specification F) tests the operability of check valves which l
act a primary coolant system pressure isolation valves and thereby reduces the potential for an intersystem loss of coolant accident.
In order to use the high pressure safety injection (HPSI) pumps to perform high pressure recirculation (HPR) following a small break loss of coolant accident i
(LOCA), successful operation of SI-MOV-24 and RH-MOV-874 is required. The monthly surveillance to be performed on these two valves willincrease the
- probability that the valves are available to perform their function during the small break LOCA. Since SI-MOV-24 will not be closed to any measurable extent during the surveillance, there will be no effect on safety injection availability.
j Surveillance on RH-MOV-874, will only last for a short time and the probability r
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E
9 of a small break loss of coolant accident concurrent with the surveillance is extremely low. If the valve becomes inoperable during this time, RH-V-783 in series with RH-MOV-874 can be closed. Therefore, there will be no measurable impact o,n HPSI system availability as a result of the surveillance.
Reference:
(1) FSAR - Section 6.3 b
4-4c i
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