Proposed Tech Specs Changes Reflecting Replacement of 125 Volt Dc Station Batteries & Chargers During Upcoming Refueling OutageML20151C414 |
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Cooper |
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03/25/1988 |
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NEBRASKA PUBLIC POWER DISTRICT |
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Shared Package |
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ML20151C408 |
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References |
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NUDOCS 8804120428 |
Download: ML20151C414 (2) |
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Category:TECHNICAL SPECIFICATIONS
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ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers ML20065K1931994-04-12012 April 1994 Proposed Tech Specs,Reflecting Removal of Definitions 1.0.Z.B.1 Through 5,change to LCO 3.21.B.1.a (Line 5) Re Ref to 10CFR20.106 & Change to Paragraphs 1,4,5 & 6 (Lines 6,3,8 & 2 Respectively) Re Ref to 10CFR20.106 ML20058N2321993-12-10010 December 1993 Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept ML20058N2881993-12-10010 December 1993 Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves ML20058M2591993-09-28028 September 1993 Proposed Tech Specs Modifying Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operation ML20056G5971993-08-31031 August 1993 Proposed TS Re Primary Containment Isolation Valve Tables ML20056G5821993-08-31031 August 1993 Proposed TS Re Primary & Secondary Containment Integrity ML20056G2341993-08-25025 August 1993 Proposed Tech Specs Bases Section to Reflect Operational & Design Changes Made to CNS Svc Water Sys During 1993 Refueling Outage ML20056F3331993-08-23023 August 1993 Proposed Tech Specs 6.0, Administrative Controls, Reflecting Creation of Mgt Position of Vice President - Nuclear ML20045D8991993-06-23023 June 1993 Proposed TS SR 4.9.A.2 Re Determination of Particulate Concentration Level of Diesel Fuel Oil Storage Tanks ML20045C0031993-06-14014 June 1993 Proposed Tech Specs Associated W/Dc Performance Criteria ML20045C8301993-06-14014 June 1993 Proposed Tech Specs Incorporating New Requirements of 10CFR20 ML20128L5561993-02-12012 February 1993 Proposed TS Table 4.2.D, Min Test & Calibr Frequencies for Radiation Monitoring Sys & TS Pages 81 & 84 Re Notes for Tables 4.2.A Through 4.2.F ML20128E6201993-02-0101 February 1993 Proposed Tech Specs Reflecting Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8331993-01-0505 January 1993 Proposed TS Pages 53,55,70 & 71,removing Bus 1A & 1B Low Voltage Auxiliary Relays ML20115F8531992-10-15015 October 1992 Proposed Tech Specs Page 48,reflecting Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3481992-10-0808 October 1992 Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee ML20104B2091992-09-0909 September 1992 Proposed TS 3.1.1 Re Reactor Protection Sys Instrumentation Requirements & TS Table 3.2.D Re Radiation Monitoring Sys That Initiate &/Or Isolate Sys ML20104A8691992-09-0202 September 1992 Proposed TS 3.9 & 4.9 Re Auxiliary Electrical Sys ML20099D4151992-07-28028 July 1992 Proposed TS 3.6 Re LCO for Primary Sys Boundary & 4.6 Re Surveillance Requirements for Primary Sys Boundary ML20113G8241992-05-0404 May 1992 Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08 ML20096D6111992-05-0404 May 1992 Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A8061992-02-25025 February 1992 Proposed Tech Specs Re Dc Power Sys 1999-06-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. 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[Table view] |
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3.9 BASCS The general objective of this Specification is to assure an adequate source of electrical power to operate the auxiliariea during plant operation, to operate facilities to cool and lubricate the plant during shutdown and to operate the engineered safegucrds following the accident. There are three sources of ac electrical energy available; namely, the startup transformer, the emergency transformer and two diesel generators. The de supply is required for switch gear and engineered safety feature systems. This supply consists of two 125V DC and two 250V DC batteries and their related chargers. Specification 3.9.A stater. the required availability of ac and de power; i.e., active off site ac sources and the required :aount of on site ac and de sources.
Auxiliary power for CNS is supplied from the startup transformer and the normal transformer. Both of these transformers are sized to carry 100% of the station auxiliary load. The emergency transformer is about one third the si=e of these two transformers and is equal in size to both emergency diesel generators.
The startup transformer and the emergency transformers are the offsice power sources. Their vo,1tage is monitored by undervoltage relays which provide low voltage protection for the erergency buses, khenever the voltage setpoint and time delay limit for the undervoltage relays have been exceeded, the emergency buses are automatically disconnected from the offsite power source.
I .5 the startup or emergency transformer is lost, the unit can continue to operate since the ur.it auxiliary transformer is in service, and the emergency or startup transformer and the diesels are available.
If both the star cup and emergency transformers become inoperable, the power level must be reduced to a value where by the unit can safely reject the load and continue to supply auxiliary electric power to the station.
In the normal mode of eperation, the startup and emergency transformers are energi:ed and two diesel generators are operable. One diesel generator may be allowed out of service based on the availability of power from the startup transformer and the fact that one diesel generator carries sufficient engineered safeguards equipment to cover all breakers. With the startup transformer and one diesel generator out of service, the off site transmission line corresponding to the emergency transformer must be available. Upon the loss of one on site and one off-site power source, power would be available from the other immediate off site power source and the two operable on site diesels to carry sufficient engineered safeguards equipment to cover all breaks. In addition to :hese two power sources, removal of the Isolated Phase Bus "quick" disconnect links would allow backfeed of power through the main transforner to the unit auxiliary transformer and provide power to carry the full station auxiliary load. The time required to perform this operation is comparable to the time the reactor could remain on RCIC operation before controlled depressuri:ation need be initiated.
Once each operating cycle , during shutdown, either a se rvic e test or performance discharge is performed on the 125 volt batteries. The performance discharge test is performed in lieu of the ser"ice test when a battery shows signs of degradation. Degradation is indicated when battery capacity drops more than 10% of rated capacity from its average on previous performance tests, nr is below 85% of the manufacturer's rating.
8804120420 880325 *198' PDR ADOCK 05000298 i
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS _
3.9.A 4.9.A (cont'd.)
- 3. The pilot cell voltage is 2.15V minimum and specific gravity 1.195 minimum, corrected for 77'F and electrolyte level.
- b. Every quarter, the following para-meters shall be verified. The actual values shall be measured and logged:
- 1. The electrolyte level of each connected cell is between the minimum and maximum level in-dication marks.
- 2. For each connected cell, the voltage is 2.15V minimum and specific gravity is 1.190 minimum, corrected for 77'F and electrolyte level. The averag+ specific gravity of B. Operation with Inoperable Equipment all connected cells will be a minimum of 1.200.
- 1. Whenever the reactor is in Run Mode or Startup Mode wi.h the reactor not in a 3. The alectrolyte temperatures Cold Condition, the availability of in a representative sanple of electric pcwer shall be as specified cells, consisting of at least in 3.9.A.1, except as specified in every sixth cell, are within 3.9.8.1. 25'F.
- a. Incoming Power c. Once each operating cycle the 125V battery charger will be tested to
- 1. From and after the date incoming power verify that the charger can supply is not available f rom a startup or emer- 200 A= peres at 125V for four hours.
gency transfor=er, continued reactor l operation is permissible under this d. Once each operating cycle, during condition for seven days. At the end shutdown, one of the following tests of this period, provided the second will be performed:
source of incoming power has not been made immediately available, the NRC 1. A battery service test to verify must be notified of the event and the that battery capacity is adequate plan to restore this second scurce. to supply the emergency load During this period, the two diesel profile, generators and associated critical buses must be demonstrated to be 2. A performance discharge test, in operable. lieu of the above service test, once every five years to verify
- 2. From and after the date that incoming that battery capacity is at least power is not available from both start- 85% of the manufacturer's rating, up and emergency transformers (i.e.,
both failed), continued operation is 3. A performance discharge test, in permissible, provided the two diesel lieu of the above service test, generators and associated critical when the battery shows signs of buses are demonstrated to be degradation or has been in service seventeen years or longer.
-195-
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