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| {{#Wiki_filter:ELECTRICAl POMER SYSTEMS SURVEILLANCE RE UIREHENTS 4.8.1.1.1 transmiss b.4.8.1.1.2 OPERABLE: a.b.Each of the above required independent circuits between the offsite ion network'and the onsite Class IE distribution system shall be: Determined OPERABLE at.least once per 7 days by verifying correct breaker alignments and indicated power availability, and.Demonstrated OPERABLE at least once per 18 months during shutdown by transferring, manually and automatically, unit, power supply from the normal circuit to the alternate circuit.Each of the above required diesel generators shall be demonstrated 4 In accordance with the frequency specified in Table'4.8.1.1.2"1 on a STAGGERED TEST BASIS by: I.Verifying the fuel level in the day fuel tank.: 2.Verifying the fuel level in the fuel storage tank.3.Verifying the fuel transfer pump s+rts and transfers fuel from the storage system to the day fue tank, a.Verifying the diese'I starts fpo$~eobient condition and accelerates to at least 900 rpm~(60 Hz)in less than or equal to 10 seconds" for OG-1 and+DG-2 and 13 seconds" for OG-3.The generator voltage and frequency shall be 4160 vo~s an 60+3.0 Hz within 10 seconds" for OG-1 and OG-2 an 13 seconds" for DG-3 after the start<signal. | | {{#Wiki_filter:ELECTRICAl POMER SYSTEMS SURVEILLANCE RE UIREHENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmiss ion network 'and the onsite Class IE distribution system shall be: |
| The diesel generator sha 1 be started for this teste%i using one of the fo11owing signals: '..~y~b)Simulated I'oss=bf-offsite power by itself.c)Simulated~l'ds's-of-offsite power in conjunction with an ESF actuation+st signa'I.d)An ESF actuation test signal by itself.5.Verifying the diesel generator is synchronized, loaded to greater than or equal to 4400 kM for OG-I and OG-2 and 2600 kM for OG-3 in less than or equal to 60 seconds", and operates with these loads for at least 60 minutes.6.Verifying the diesel generator is aligned to provide standby.power to the associated emergency busses.7.Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 230 psig for OG-1 and OG-2 and 200 psig for OG-3.At least once per 31 days and after each operation of the diesel where the period of ooeration was greater than or equal to 1 hour by checking for and removing accumulated water from the day fuel tanks."These diesel generator starts froi-, ambient conditions shall be performed at leas.once per 184 days in these surveillance tests and all other engine star s for the purpose oi his surveillance testing shall be preceded by an engine pr elube oeriod and/or other warmup pr ocedures recommended by the manu-facturer so that mechanical stress and~ear on he diesel engine is minimized. | | Determined OPERABLE at .least once per 7 days by verifying correct breaker alignments and indicated power availability, and. |
| MASHrNGTON NUCLEAR" UNIT 2..3/4 8-3 r.menlient 4 8505290490 850522 ADOCn 05000S97~PDR ELECTRICAL POMER SYSTEMS SURVEILLANCE RE UIREHENTS Continued 4.Simulating a loss-of-offsite power by itself, and: a)For divisions 1 and 2: 1)Verifying deenergization of the emergency busses and load shedding from the emergency busses.b)2)Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the autoconnected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads, After energization, the steady tate voltage and frequency of the emergency busses ll be maintained at 4160~420 volts and 60 t~~~z during this test.For divi': 1)Veri f deenergization of the emergency bus.2)Verifyin~~diesel generator starts on the auto-start signal, en zes the emergency bus with the perma-nently connected loads within 13 seconds and operates for greater tha r equal to 5 minutes while its generator is lo with the shutdown loads.After energization, th ady"state voltage and frequency of the emergency b~all be maintained at 4160+420 volts and 60+WO Hz during this test.0ov'D<l-l awd DCq-2>Ov4 4l4 e+4ZO VoAa 0~40~OAZ4r DCq-~5.6.Verifying that on an ECCS actuation test signal, without loss-" of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.The generator voltage and frequency shall be 4160+"~Qtf volts and 60 a 3.0 Hz within 10 seconds after the auto-ar signa;e s ea y-state generator voltage and frequency 4 lloo~4zo v01%~h bb~'5.0 0+Simulating a loss-of-offsite power in conjunction with an ECCS actuation test signal, and: a)For divisions 1 and 2: 1)Verifying deenergization of the emergency busses and loads shedding from the emergency busses.2)Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected loads through the load sequencer and operates WASHINGTON NUCLEAR-UNIT 2 3/4 8-5 0~SI,~ | | : b. Demonstrated OPERABLE at least once per 18 months during shutdown by transferring, manually and automatically, unit, power supply from the normal circuit to the alternate circuit. |
| vs sss w~SWsev S ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160~420 volts and 60+3.0 Hz during this test.7.b)For division 3: 1)Verifying deenergization of the emergency bus.2)Verifying the diesel generator starts on the auto-start signal, energizes the emergency bus with the permanently connected loads and t auto-connected emergency loads within 30 seconds a'ates for greater than or equal to 5 minutes e its generator is loaded with the emergency lo~After energization, the steady state voltage and equency of the emergency bus shall be maintained t 4160+420 volts and 60+3.0 Hz during this Verifying that all~atic diesel generator trips are automatically bypa upon loss of voltage on the emergency bus concurrent w+n ECCS actuation signal except: a)For divi 1 and 2, engine overspeed and generator differ 1 current, incomplete starting sequence and emerge manual stop.b)For division 3, engine overspeed, generator differential current and emergency manual stop.8.Oltoo+4ZO VO'lb md f<+.O Q~Nlhhi<Verifying the diesel generator operates for at least 24 hours.During the first 2 hours of this test, the diesel generator shall be loaded to greater than or equal to 4650 kW for OG-1 and OG"2 and 2850 kW for DG-3.During the remaining 22 hours of this test, the diesel generator shall be loaded to 4400 kW+~for DG-1 and OG-2 and 2600 kW fo DG-3.The enerator voltage-250 and frequency shall be 4160 vo s and x 3.0 Hz wit in 10 seconds for DG-1 and DG-2 and 13 seconds for OG-3 after the art signa;the steady-state generator voltage and frequency shall be maintained within~4hese-Sion~ | | 4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE: 4 |
| during this test.4iho+4@0 VOHa O d k 043 O Sa Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4.8.1.l.2.e.4.a)2)and b)2).""If Surveillance Requirements 4.8.1.l.2.e.4.a)2)and/or b)2)are not satis-factorily completed, it is not necessary to repeat the preceding 24-hour test.Instead, the diesel generator may be operated at 4400 kW for OG-1 or OG-2 or 2600 kW for OG-3 for 1 hour or until operating temperature has stabilized. | | : a. In accordance with the frequency specified in Table'4.8.1.1.2"1 on a STAGGERED TEST BASIS by: |
| WASHINGTON NUCLEAR-UNIT 2 3/4 8"6 I~I 0 v'I p4 JI}} | | I. Verifying the fuel level in the day fuel tank.: |
| | : 2. Verifying the fuel level in the fuel storage tank. |
| | : 3. Verifying the fuel transfer pump s+rts and transfers fuel from the storage system to the day fue tank, |
| | : a. Verifying the diese'I starts fpo$ ~eobient condition and accelerates to at least 900 rpm~(60 Hz) in less than or equal to 10 seconds" for OG-1 and+DG-2 and 13 seconds" for OG-3. The generator voltage and frequency shall be 4160 vo ~s an 60 + 3.0 Hz within 10 seconds" for OG-1 and OG-2 an 13 seconds" for DG-3 after the start<signal. The diesel generator sha be started for this teste%i using one of the fo11owing signals: |
| | 1 |
| | '.. ~ y~ |
| | b) Simulated I'oss=bf-offsite power by itself. |
| | c) Simulated ~l'ds's-of-offsite power in conjunction with an ESF actuation+st signa'I. |
| | d) An ESF actuation test signal by itself. |
| | : 5. Verifying the diesel generator is synchronized, loaded to greater than or equal to 4400 kM for OG-I and OG-2 and 2600 kM for OG-3 in less than or equal to 60 seconds", and operates with these loads for at least 60 minutes. |
| | : 6. Verifying the diesel generator is aligned to provide standby |
| | . power to the associated emergency busses. |
| | : 7. Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 230 psig for OG-1 and OG-2 and 200 psig for OG-3. |
| | : b. At least once per 31 days and after each operation of the diesel where the period of ooeration was greater than or equal to 1 hour by checking for and removing accumulated water from the day fuel tanks. |
| | "These diesel generator starts froi-, ambient conditions shall be performed at leas. once per 184 days in these surveillance tests and all other engine star s for the purpose oi his surveillance testing shall be preceded by an engine pr elube oeriod and/or other warmup pr ocedures recommended by the manu-facturer so that mechanical stress and ~ear on he diesel engine is minimized. |
| | MASHrNGTON NUCLEAR " UNIT 2 .. 3/4 8-3 r.menlient 4 8505290490 850522 ADOCn 05000S97~ |
| | PDR |
| | |
| | ELECTRICAL POMER SYSTEMS SURVEILLANCE RE UIREHENTS Continued |
| | : 4. Simulating a loss-of-offsite power by itself, and: |
| | a) For divisions 1 and 2: |
| | : 1) Verifying deenergization of the emergency busses and load shedding from the emergency busses. |
| | : 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the autoconnected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads, After energization, the steady tate voltage and frequency of the emergency busses b) For 1) |
| | ~ |
| | divi ll Veri f |
| | ':be maintained at 4160 ~ 420 volts and 60 z during this test. |
| | ~ |
| | ~ |
| | deenergization of the emergency bus. |
| | t |
| | : 2) Verifyin ~~diesel generator starts on the auto-start signal, en zes the emergency bus with the perma-nently connected loads within 13 seconds and operates for greater tha r equal to 5 minutes while its generator is lo with the shutdown loads. After energization, th ady"state voltage and frequency of the emergency 420 volts and 60 + |
| | b ~all be maintained at 4160 + |
| | WO Hz during this test. |
| | : 5. Verifying that on an ECCS actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. |
| | Qtf volts The generator voltage and frequency shall be 4160 + |
| | and 60 a 3.0 Hz within 10 seconds after the auto- |
| | "~ |
| | ar signa ; e s ea y-state generator voltage and frequency 0ov 'D<l-l awd DCq-2> 4 lloo ~ 4zo v01% ~h bb~'5.0 0+ |
| | Ov4 4l4 e+4ZO VoAa 6. Simulating a loss-of-offsite power in conjunction with an ECCS actuation test signal, and: |
| | 0 ~ 40~OAZ4r DCq-~ a) For divisions 1 and 2: |
| | : 1) Verifying deenergization of the emergency busses and loads shedding from the emergency busses. |
| | : 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected loads through the load sequencer and operates WASHINGTON NUCLEAR - UNIT 2 3/4 8-5 |
| | |
| | 0 ~ |
| | SI, ~ |
| | |
| | vs sss w ~ SWsev S |
| | ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 ~ |
| | 420 volts and 60 + 3.0 Hz during this test. |
| | b) For division 3: |
| | : 1) Verifying deenergization of the emergency bus. |
| | : 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency bus with the permanently connected loads and t auto-connected emergency loads within 30 seconds a 'ates for greater than or equal to 5 minutes e its generator is loaded with the emergency lo ~ After energization, the steady state voltage and equency of the emergency bus shall be maintained t 4160 + 420 volts and 60 + 3. 0 Hz during this |
| | : 7. Verifying that all ~atic diesel generator trips are automatically bypa upon loss of voltage on the emergency bus concurrent w+ n ECCS actuation signal except: |
| | a) For divi 1 and 2, engine overspeed and generator differ 1 current, incomplete starting sequence and emerge manual stop. |
| | b) For division 3, engine overspeed, generator differential current and emergency manual stop. |
| | : 8. Verifying the diesel generator operates for at least 24 hours. |
| | During the first 2 hours of this test, the diesel generator shall be loaded to greater than or equal to 4650 kW for OG-1 and OG"2 and 2850 kW for DG-3. During the remaining 22 hours of this test, the diesel generator shall be loaded to 4400 kW +- ~ |
| | for DG-1 and OG-2 and 2600 kW fo DG-3. The enerator voltage 250 and frequency shall be 4160 vo s and x 3.0 Hz wit in 10 seconds for DG-1 and DG-2 and 13 seconds for OG-3 after the art signa ; the steady-state generator voltage and frequency Oltoo+4ZO VO'lb md shall be maintained within~4hese-Sion~ during this test. |
| | f <+.O Q~ Nlhhi< 4iho+ 4@0 VOHa O d k 043 O Sa Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4. 8. 1. l. 2. e. 4. a)2) and b)2). " |
| | "If Surveillance Requirements 4. 8. 1. l. 2. e. 4. a)2) and/or b)2) are not satis-factorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at 4400 kW for OG-1 or OG-2 or 2600 kW for OG-3 for 1 hour or until operating temperature has stabilized. |
| | WASHINGTON NUCLEAR - UNIT 2 3/4 8"6 |
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| | I~ I0 'I v |
| | p4 JI}} |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A7561995-04-25025 April 1995 Proposed Tech Specs,Adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A6541995-02-10010 February 1995 Proposed Tech Specs,Modifying Surveillance Acceptance Criteria from 10% to 20% for Individual Jet Pump diffuser- to-lower Plenum Differential Pressure Variations of Individual Jet Pump from Established Patterns ML17291A4811994-10-31031 October 1994 Proposed Tech Spec Relocating Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4781994-10-31031 October 1994 Proposed Tech Spec 3/4.1.3.1, Reactivity Control Sys. ML17291A4451994-10-12012 October 1994 Corrected Proposed TS Bases 3/4.2.6, Power/Flow Instability. ML17291A4221994-09-26026 September 1994 Proposed Tech Specs,Reflecting Use of Siemens Power Corp Staif Code for Stability Analysis,Per Ieb 88-007,Suppl 1 ML17291A3981994-09-18018 September 1994 Proposed TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3191994-08-0808 August 1994 Proposed Tech Specs 4.0.5 Re Guideliness for Inservice Insp & Testing Program ML17291A2171994-07-12012 July 1994 Proposed Tech Specs for Relocation of TS Tables for Instrument Response Time Limits ML17291A2221994-07-0808 July 1994 Proposed TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17291A1561994-06-23023 June 1994 Proposed Tech Specs Re Supporting Hydrostatic Testing 1999-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
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ELECTRICAl POMER SYSTEMS SURVEILLANCE RE UIREHENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmiss ion network 'and the onsite Class IE distribution system shall be:
Determined OPERABLE at .least once per 7 days by verifying correct breaker alignments and indicated power availability, and.
- b. Demonstrated OPERABLE at least once per 18 months during shutdown by transferring, manually and automatically, unit, power supply from the normal circuit to the alternate circuit.
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE: 4
- a. In accordance with the frequency specified in Table'4.8.1.1.2"1 on a STAGGERED TEST BASIS by:
I. Verifying the fuel level in the day fuel tank.:
- 2. Verifying the fuel level in the fuel storage tank.
- 3. Verifying the fuel transfer pump s+rts and transfers fuel from the storage system to the day fue tank,
- a. Verifying the diese'I starts fpo$ ~eobient condition and accelerates to at least 900 rpm~(60 Hz) in less than or equal to 10 seconds" for OG-1 and+DG-2 and 13 seconds" for OG-3. The generator voltage and frequency shall be 4160 vo ~s an 60 + 3.0 Hz within 10 seconds" for OG-1 and OG-2 an 13 seconds" for DG-3 after the start<signal. The diesel generator sha be started for this teste%i using one of the fo11owing signals:
1
'.. ~ y~
b) Simulated I'oss=bf-offsite power by itself.
c) Simulated ~l'ds's-of-offsite power in conjunction with an ESF actuation+st signa'I.
d) An ESF actuation test signal by itself.
- 5. Verifying the diesel generator is synchronized, loaded to greater than or equal to 4400 kM for OG-I and OG-2 and 2600 kM for OG-3 in less than or equal to 60 seconds", and operates with these loads for at least 60 minutes.
- 6. Verifying the diesel generator is aligned to provide standby
. power to the associated emergency busses.
- 7. Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 230 psig for OG-1 and OG-2 and 200 psig for OG-3.
- b. At least once per 31 days and after each operation of the diesel where the period of ooeration was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water from the day fuel tanks.
"These diesel generator starts froi-, ambient conditions shall be performed at leas. once per 184 days in these surveillance tests and all other engine star s for the purpose oi his surveillance testing shall be preceded by an engine pr elube oeriod and/or other warmup pr ocedures recommended by the manu-facturer so that mechanical stress and ~ear on he diesel engine is minimized.
MASHrNGTON NUCLEAR " UNIT 2 .. 3/4 8-3 r.menlient 4 8505290490 850522 ADOCn 05000S97~
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ELECTRICAL POMER SYSTEMS SURVEILLANCE RE UIREHENTS Continued
- 4. Simulating a loss-of-offsite power by itself, and:
a) For divisions 1 and 2:
- 1) Verifying deenergization of the emergency busses and load shedding from the emergency busses.
- 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the autoconnected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads, After energization, the steady tate voltage and frequency of the emergency busses b) For 1)
~
divi ll Veri f
':be maintained at 4160 ~ 420 volts and 60 z during this test.
~
~
deenergization of the emergency bus.
t
- 2) Verifyin ~~diesel generator starts on the auto-start signal, en zes the emergency bus with the perma-nently connected loads within 13 seconds and operates for greater tha r equal to 5 minutes while its generator is lo with the shutdown loads. After energization, th ady"state voltage and frequency of the emergency 420 volts and 60 +
b ~all be maintained at 4160 +
WO Hz during this test.
- 5. Verifying that on an ECCS actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.
Qtf volts The generator voltage and frequency shall be 4160 +
and 60 a 3.0 Hz within 10 seconds after the auto-
"~
ar signa ; e s ea y-state generator voltage and frequency 0ov 'D<l-l awd DCq-2> 4 lloo ~ 4zo v01% ~h bb~'5.0 0+
Ov4 4l4 e+4ZO VoAa 6. Simulating a loss-of-offsite power in conjunction with an ECCS actuation test signal, and:
0 ~ 40~OAZ4r DCq-~ a) For divisions 1 and 2:
- 1) Verifying deenergization of the emergency busses and loads shedding from the emergency busses.
- 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected loads through the load sequencer and operates WASHINGTON NUCLEAR - UNIT 2 3/4 8-5
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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 ~
420 volts and 60 + 3.0 Hz during this test.
b) For division 3:
- 1) Verifying deenergization of the emergency bus.
- 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency bus with the permanently connected loads and t auto-connected emergency loads within 30 seconds a 'ates for greater than or equal to 5 minutes e its generator is loaded with the emergency lo ~ After energization, the steady state voltage and equency of the emergency bus shall be maintained t 4160 + 420 volts and 60 + 3. 0 Hz during this
- 7. Verifying that all ~atic diesel generator trips are automatically bypa upon loss of voltage on the emergency bus concurrent w+ n ECCS actuation signal except:
a) For divi 1 and 2, engine overspeed and generator differ 1 current, incomplete starting sequence and emerge manual stop.
b) For division 3, engine overspeed, generator differential current and emergency manual stop.
- 8. Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 4650 kW for OG-1 and OG"2 and 2850 kW for DG-3. During the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to 4400 kW +- ~
for DG-1 and OG-2 and 2600 kW fo DG-3. The enerator voltage 250 and frequency shall be 4160 vo s and x 3.0 Hz wit in 10 seconds for DG-1 and DG-2 and 13 seconds for OG-3 after the art signa ; the steady-state generator voltage and frequency Oltoo+4ZO VO'lb md shall be maintained within~4hese-Sion~ during this test.
f <+.O Q~ Nlhhi< 4iho+ 4@0 VOHa O d k 043 O Sa Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4. 8. 1. l. 2. e. 4. a)2) and b)2). "
"If Surveillance Requirements 4. 8. 1. l. 2. e. 4. a)2) and/or b)2) are not satis-factorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at 4400 kW for OG-1 or OG-2 or 2600 kW for OG-3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temperature has stabilized.
WASHINGTON NUCLEAR - UNIT 2 3/4 8"6
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