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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210R8051999-08-10010 August 1999 Startup Test Rept for Cycle 7 ML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217Q1111998-02-25025 February 1998 Rev 18 to Odcm ML20211F4401997-09-26026 September 1997 Cycle 6 Startup Test Rept for Seabrook Station,Unit 1 ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20195J1451997-07-23023 July 1997 Rev 15 to Seabrook Station Operating Experience Manual (Ssoe) ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20148K1251997-05-0707 May 1997 Rev 6 to Part I, Seabrook Station Pump & Valve IST Program Plan ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20138J3351996-12-19019 December 1996 Rev 16 to Offsite Dose Calculation Manual ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20115J7481996-03-26026 March 1996 Procedure for Ultrasonic Examination of Centrifugally Cast Stainless Steel Piping Using Low Frequency SAFT-UT System ML20138J3621996-03-21021 March 1996 Process Control Program ML20100G8351996-02-16016 February 1996 Startup Test Rept,Cycle 5. W/ ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20083K7351995-04-19019 April 1995 Rev 74 to Emergency Response Manual (Sser) ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20081J6021995-03-22022 March 1995 Revised Table A.3-1, Radioactive Liquid Waste Sampling & Analysis Program, to ODCM ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20079B2491994-12-27027 December 1994 Proposed Changes to Part a of ODCM 1999-08-10
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217Q1111998-02-25025 February 1998 Rev 18 to Odcm ML20195J1451997-07-23023 July 1997 Rev 15 to Seabrook Station Operating Experience Manual (Ssoe) ML20148K1251997-05-0707 May 1997 Rev 6 to Part I, Seabrook Station Pump & Valve IST Program Plan ML20138J3351996-12-19019 December 1996 Rev 16 to Offsite Dose Calculation Manual ML20115J7481996-03-26026 March 1996 Procedure for Ultrasonic Examination of Centrifugally Cast Stainless Steel Piping Using Low Frequency SAFT-UT System ML20138J3621996-03-21021 March 1996 Process Control Program ML20083K7351995-04-19019 April 1995 Rev 74 to Emergency Response Manual (Sser) ML20081J6021995-03-22022 March 1995 Revised Table A.3-1, Radioactive Liquid Waste Sampling & Analysis Program, to ODCM ML20079B2491994-12-27027 December 1994 Proposed Changes to Part a of ODCM ML20078M1161994-11-16016 November 1994 Rev 1 to IST Reference ML20065Q7571993-09-24024 September 1993 Station Offsite Dose Calculation Manual, Rev 13 ML20062L1901993-09-15015 September 1993 Public Version of Rev 6 to State of Me Ingestion Pathway Plan for Seabrook Station ML20127P4721993-01-25025 January 1993 Rev 5 to New Hampshire Traffic Mgt Manual ML20101B2601992-05-15015 May 1992 Rev 0 to Turbine Overspeed Protection Maint & Testing Program,Seabrook Unit 1 Nuclear Power Station ML20090B0331991-12-18018 December 1991 Rev 10 to Odcm ML20086J2241991-10-31031 October 1991 Rev 4 to New Hampshire Radiological Emergency Response Plan, Traffic Mgt Manual ML20085K1961991-10-31031 October 1991 Commonwealth of Massachusetts Public Alert & Notification Sys Conversion Proposal, Consisting of Rev 0 to Site Svc Procedures 91337,91336 & 91338.W/18 Oversize Drawings ML20079M4551991-10-31031 October 1991 Rev 4 to Maine Ingestion Pathway Plan,Reflecting Changes to Div of Health Engineering (Dhe) Procedure 2.01 Contained in App D of Plan.Rev Consists of Changes to Dhe Personnel Call Lists & to Method of Notification ML20090B0371991-10-24024 October 1991 Rev 9 to Odcm ML20090B0411991-07-0808 July 1991 Rev 8 to Odcm ML20077H0371991-06-26026 June 1991 Plan for Massachusetts Communities,App M, 'New Hampshire Yankee Offsite Emergency Resource Manual.' ML20079C6681991-05-13013 May 1991 Program Description for Reverification of Pullman-Higgins Field Weld Records ML20073H9871991-04-29029 April 1991 Rev 0 to Procedure for Review of Radiographic Records ML20073E1201991-04-26026 April 1991 Rev 0 to 83A5643, Procedure for Review of Drawings. Purchase Order 76945 & Consulting Svcs Agreement Encl ML20073E1041991-04-26026 April 1991 Rev 0 to 83A5642, Procedure for Review of Radiographs ML20073E1451991-02-28028 February 1991 Revised Seabrook Station Special Conditions for Security Clearance for Unescorted Access. Safety Handbook Encl ML20082L7781991-02-28028 February 1991 Rev 7 to Station Odcm ML20065M9071990-12-0404 December 1990 Rev 57 to Production Emergency Response Manual,Including Rev 14 to Er 5.2 & Rev 1 to Er 5.8 ML20062C8551990-10-26026 October 1990 Revised Draft Odcm ML20055G3031990-06-14014 June 1990 Rev 3 to State of Me Ingestion Pathway Plan (Mipp) for Seabrook Station ML20062C8591990-01-31031 January 1990 ODCM Atmospheric Diffusion & Deposition Factors ML19353B2181989-12-0606 December 1989 Rev 0 to Seabrook Station Evacuation Time Study Handbook. ML19332D0051989-08-17017 August 1989 Rev 18 to Operations Mgt Manual (Opmm). ML20247R2101989-06-21021 June 1989 Field Change 1 to Rev 2 to Startup Test Procedure 1-ST-22, Natural Circulation Test. Related Info Encl ML20247N4011989-03-20020 March 1989 Rev 2 to Startup Test Procedure 1-ST-22, Natural Circulation Test ML20151T6441988-07-22022 July 1988 Environ Qualification Testing of Coaxial Instrument Cables (RG 58) ML20151T6211988-07-21021 July 1988 Test Rept for Environ Qualification Testing of Coaxial Instrument Cables (RG 58) ML20151T5911988-06-22022 June 1988 Rev 1 to Test Procedure for Environ Qualification Testing of Coaxial Instrument Cables (RG 58) ML20151B9181988-05-25025 May 1988 Test Procedure for Environ Qualification Testing of Coaxial Instrument Cables (RG 58) for New Hampshire Yankee ML20247M2791988-02-24024 February 1988 Rev 3 to Station Operating Procedure Rs 0722, New Fuel Receipt & Insp ML20247M2901988-02-24024 February 1988 Rev 3 to Station Operating Procedure Rs 0723, New Fuel Shipment ML20149F9351987-10-31031 October 1987 Rev 1 to YAEC-1546, Seabrook Metpac:Computer Software Package Which Evaluates Consequences of Offsite Radioactive Release Written for Seabrook Nuclear Power Station, User Manual ML20149F9591987-10-31031 October 1987 YAEC-1619, HP-41CX Calculator Eprom Sys:Dose Projection Software Package Which Evaluates Consequences of Offsite Radioactive for Seabrook Nuclear Power Station at Seabrook,Nh, Users Manual ML20234E0561987-09-18018 September 1987 Rev 0 to Emergency Plan Implementing Procedures for Massachusetts Communities,Including IP 1.1, New Hampshire Yankee Offsite Response Director/Assistant, IP 1.2, Radiological Health Advisor & IP 1.7, Technical Advisor ML20247N3661987-05-14014 May 1987 Rev 2 to Stpd, Seabrook Station Startup Test Program Description ML20211M7181987-02-13013 February 1987 State of Me Ingestion Pathway Plan for Seabrook Station, Seabrook,Nh ML20206U5561986-12-31031 December 1986 Revised Nuclear Incident Advisory Team Handbook ML19327B2681986-10-15015 October 1986 Rev 2 to Detailed Sys Text, Steam Dump Sys. ML20211E5741986-10-14014 October 1986 Rev 0 to General Test Procedure GT-M-106, Containment & Containment Encl Surface Insp. Related Documentation Encl ML20212N5461986-08-31031 August 1986 Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational Testing 1998-02-25
[Table view] |
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INSTRUCTISNS OEx-4emA d/.2 066
, PROTECTIVE SYSTEM l
GENERAL of devices, all components of the Mechanical-Hy-draulic Trip System
'itepurposecf the Protective Systemis to detect undestrahle or dangerous operating conditions of the turbine-generator, tag apprtspriate trip actions, a. Mechanical Shut-Off Velve (MSOV) and p ovide information *o the operator about the t detected conditions and the consequent actions. In b. Mechanical Trip Valve (MTV) addition, mecns are provided for lestingall testable equipment and circutts. c. Mecharical I4ckout Solenoid Vahe (MLV) l I
The Protective System consists of two major d. Dectrical Mp van m) subsy stems;
- e. Electrical Lockout Solenoid Valve (ELV) 1 %e Mecharical-Ifydraulic Trip System -
described in detail in the Wrbine Section of no MSOV and MTV arecontrolled hydenlically the Instruct 19n Book, by the Mechacical Trip Pilot Valve (MTPV), and when their pilot iltes are depresst rized, these l 2. De Electrical Trip and Monitoring System valves shut off their irput lir.e and drata their out-l (T&M) - described in detail in the Electro- put line, tripping the ETS.
! hydraulic Secticn of the Instructico Dook.
De MLV is controlled electrically by the TLM.
'C_ nis instruction describes in summary both sub- andwhen energized, itbypasses the MSOV and MTV, i
systems and their relationships, permitting these two valves and two of the three signal paths that actuate them to be tested without A simplified signal flow diagram of the Protec- tripping the ETS.
tive System is shown in l'igure 1.
'Ihe ETV ls cortrolled hydraulicallyby the Elec-trical Trip Solencid Valve (ETSV), and when its pilot PRINCIPLE OF OPERATION line is depressurized, this valve shi.ta off its input line and drains its output line, trippirg the ETS, ne Emergene? Trip System (ETS) is the high-pressure fluid system that, when in the Heset or De ELV is controlled electrically by the T&M, pressurized state, permits all ofeamvalves to open and, when energized, bypasses the ETV permitting in the presence of opening signals from the EHC. this valve and the signal path that actuates it to be When in the tripped or depressurized state, it over- tested without tripping the ETS.
ridesallopeningsignals, and trips the Main and He-heatStop Valves, the Control Valves, and the Inter. In order to trip the ETS, any tripping signalhas C cept Valves directly by way of their disc-dump to actuate or.e or both of the MTPV or the ETSV.
s ulves, and trips the Extraction Check Valves Each of these two caseswill be examined separately, thn. ugh the Air Relay Dump Valve. %e principal outputfuncitonof the Protective Systemis to control the state of the ETS. 1, MTPV ACTUATION nis valve is operated mechanically by the I. MECHANICAL-IIYDRAULIC TRIP SYSTEM Trip Latch Hod, which is tripped (i.e., (1-lowed to move under the influence of a charged
%e ETS is pressurized from the high-pressure spring to a position where the M TPV is tripped) l hydraulle flufd supply, through the following chain by the Trip l'inger.
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PROTECTIVE SYSTEM, GEK-46487A The Trip Finger is operated by: which are connected to the T&M and provide infor-mation about the state of the various components
- a. The Mechanical Overspeed Trip Device (valves, piston, Trip Latch Rod, MTH, etc.).
(OST)
This is actuated *duringan overspeedof the H. ELECTRICAL TRIP AND MONITORING SYS-turbine exceeding the OST setting, or at TEM (T&M) rated speedduring aMcchanicalOverspeed TripTest. During thistest the T&M ener- The principal function of this part of the Protec-gizes the Oil Trip Solenoid Valve (OTSV) tive System is to connect all external trip signals which admits lubrication oil to the OST (except the trippingsignals from the OST and MTH, f causing it to trip. A coordinated actuation which actdirectly onthe Mechanical-Hydraulic Trip i of the MLV preventsthe ETS from tripping. System) to one or both of the MTSV and ETSV after suitah!e modifications by logic circuits. Each of
- b. The Mechanical Trip Piston (MTP) these valvesis independentlycapable of tripping the ETS.
This is he'd in the reset position by tur-bine lube oil pressure. The piston is al- The incoming trip signals are arrant;ed into two lowed to trip by actionof a springwhen the groups:
oil pressure is lost or when the oil is shut off by the Mechanical Trip Solenoid Valve 1. Signals I:xternal to the EHC Cabinet:
(MTSV) . This valve is energized by the T&M during a 125V trip as it will be de- These cause 125V Trips;i.e., they activate fined later, or during a MTP Test. In the the 125V Trip Bus and energize the MTSV latter case a coordinated actuation of the directly.
MLV prevents the ETS from tripping,
- c. The Manual Trip Handle (MTH) In addition, the 24V trip circuit is indirectly operated through a set of relays (crosstrip),
There is no provision for testing the MTH and the 125V Trip Bus is locked up after a
(- under lockout conditions. An MTH test short time delay, will result in an actual trip.
When the generator circuit breaker is open, The Trip Latch Rod, once tripped, latches and the MTV and ETS are tripped, an addi-mechanically, and remains in the tripped posi- tional lock-up circuit is established through tion even after the condition that caused it to pressure switch contacts, trip (a, b, or c) hasbeen cleared. It is reset by the Reset Mechanism, consisting of: During a MTP Test the MTSV is energized without activating the 125V Trip Bus, the cross
- a. De Oil Reset Solenoid Valve (ORSV) - trip circuit and the lock-up circuits, when energized by the T&M actuates the Oil Reset Piston. 2. Signals internal to the EHC Cabinet:
- b. The Oil Reset Piston (ORP) - resets the These cause a 24V trip, i.e., they de-ener-Trip Latch Rod and the MTPV, which in gize the ETSV solenoids througha set of re-turn resets the MSOV and MTV. layscor. tacts, and lock-up the 24V tripcircuit through another set of relays contacts.
- 2. ETSV ACTUATION The first set of relays is also operatedduring a Trip Anticipator action (if applicable) or dur-His valvehastwo 24 VDC solenoidswhichare ing an Electrical Trip Test;in these two cases normally energized when the ETSV is in the thelock-up circuitis notactivatedand the sit-reset state. The valve trips when both sole- uation is cleared once the cause producing it nolds are de-energized. Pallure of one sole- is removed, without necessitatingany positive noid willnot cause aspurioustrip. The sole- resetting action, noids are connected to the T&M and are de-energized during a 24V trip as willbe defined Of the signalsinternal tothe EHC Cabinet, the later, duringa Trip Anticipator action (if ap- Loss of Both $eed Signal and the Back-Up plicable), or during an Electrical Trip Test. Overspeed Trip Signalenergize, in addition to In the latter case, a co-ordinatedactuation of the trippingand the lockingrelays, a third set
(.~ the ELY prevents the ETS from tripping. of relays whicheross trip the 125V Trip Bus.
The other three signals that cause a 24V trip The Mechanical-Hydraulic Trip System includes a do not energize these cross trip relays; how-number of pressure switches and limit switches ever of these, the Master Trip Button causes 3
~ .. . -. - .-- - --..- ... . .
GEK-46487A, PROTECTIVE SYFTEM q
a 125V Trip thr0cgha separate contract, The The T4M also cor.tains the Icgic for testing the /
Customer, at his option, can do the same for trip devices. (Mechanical Overtpced, Mechanical Customer Trips energizedbythe 125V Station Trip Pisten and Electrical Triptests.) When one of Battery. On_ ly the lcss o( 125 VDC when speed these tests is initiated, the TLM logic provides a is below 75% of rated inevitably produces a soquence of signalsto the appropria*elockout, trip, 24V Trip alone. and reset valve solenoids and receives feedback signals that allow it to sense the status of the Me-A loss of 24 VDC de-encrgizes the ETSV chanical-Hydraulic Trip System aftereach step and solenoids, causing a 24V Trip andeross trips whether the test was successful.
the 125V Trip B us.
In summary, all trip signals to the tam, ex- Each of the fhree Back-Up Overspeed Trip Cir-
)
^
cept the loss of 125 VDC, and - if the customer so cults can be separately tested without causing an chooses - the customer trips operated with station actual trip. These circuits, as well as many other battery, activate two independent paths throughout trip circuits of the T&M, are arranged in a two-the T&M and the Mechanical-Hydraulic Trip Sys- out-of-three Icgic system.
tem, and redundantly trip ine ETS.
When the condition that caused atrip has cleared, The Thrust Bearing Wear Detector is tested via the Elic can be reset bydepressingthe Reset Button an automatic system from the contrei panel, on the Turbine panel. This will:
Finally, the T&M System contains logic for the
- a. Dreak the lock-up circuits, display of the status of the ETS, Mechanical-Hy-
- b. Reset the MTV throughthe Reset Mechanism, draulic System, and T&M itself, logic for annun-clation and First Hit Detection of tripping and other The Reset button must be held down until the "RE- abnormalconditions, and provides switchingsignals SET" lightcomes on toasaare the ETS pressure has for control functions to other sections of the EllC been re-established, and for customer use. .
J t
10-76 (1M)
GENER AL $ ELECTRIC T