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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
[Table view] |
Text
List of Affected Pages for Proposed Tech. Spec. Amendment To Remove Requirements Related to Seismic Monitoring Instrumentation
~Pa e ~ec ion Descri tion of Chan e v1 Index Delete TS Section 3/4.3.7 line listing Seismic Monitoring Instrumentation.
x111 Index Delete Bases Section 3/4.3.7 line listing Seismic Monitoring Instrumentation.
xxll Index Delete references to Tables 3.3.7.2-1, "Seismic Monitoring Instrumentation," and 4.3.7.2-1, "Seismic Monitoring Instrumentation Surveillance Requirements."
3/4 3-61 thru Instrumentation- Delete Specification 3.3.7.2, 4.3.7.2.1, and 3/4 3-63 Seismic Monitoring Instr. 4.3.7.2.2, Seismic Monitoring Instrumentation LCO and Surveillance Requirements B 3/4 3-5 Bases -Instrumentation Delete 3/4.3.7.2, "Seismic Monitoring Instrumentation."
N *NN h Rli The following note shall be placed in the center of page 3/4 3-61, and pages 3/4 3-62-and 3/4 3-63 will no longer exist.
Note: Pages 3/4 3-62 and 3/4 3-63 have been deleted Page 3/4 3-64 shall be placed on the obverse side of page 3/4 3-61.
@401 14019~ 945DOD0297
INDEX LIMITING CONOITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 3 INSTRUMENTATION 3/4.3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3/4 3"1 3/4.3. 2 ISOLATION ACTUATION INSTRUMENTATION.................. 3/4 3-10 3/4.3.3 EHERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION...................................... 3/4 3-25 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation.. 3/4 3-37 End-of-Cycle Recirculation Pump Trip System Instrumentation...................................... 3/4 3"41 3/4.3. 5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................................... 3/4 3"47 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION........... ....... 3/4 3-52 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................. 3/4 3-58 Meteorological Monitoring Instrumentation............ 3/4 3"64 Remote Shutdown Monitoring Instrumentation........... 3/4 3-67 Accident Monitoring Instrumentation..... 3/4 3-70 Source Range Monitors................................ 3/4 3-76 Traversing In-Core Probe System...................... 3/4 3-77 Loose-Part Detection System.......................... 3/4 3"78 F',plosive Gas Monitoring Instrumentation............. 3/4 3-79 3/4.3.8 TURBINE OVERSPEEO PROTECTION SYSTEM................... 3/4 3-82 3/4.3.9 FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEH'ACTUATION INSTRUMENTATION..... 3/4 3-84 WASHINGTON NUCLEAR " UNIT 2 vi Amendment No. Ig>> DD
coNTRGLtHihcopY BASES SECTION PAGE INSTRUMENTATIQN (Continued) 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....'........ B 3/4 3-4 me ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ P ~ ~
Meteorological Honitoring Instrumentation....... B 3/4 3-5 Remote Shutdown Monitoring Instrumentation...... B 3/4 3-5 Accident Monitoring Instrumentation............. B 3/4 3-5 Source Range Monitors........................... B 3/4 3-5 Traversing In-Core Probe System................. B 3/4 3-5 Loose-Part Detection System..................... B 3/4 3-6 Explosive Gas Monitoring Instrumentation........ B 3/4 3-6 3/4.3.B TURBINE OVERSPEED PROTECTION SYSTEH............. B 3/4 3-6 3/4.3. 9 FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION....................... B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEH 3/4.4.1 RECIRCULATION SYSTEM............................ B 3/4 4-1 3/4.4.2 SAFETY/RELIEF VALVES............................ B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEH LEAKAGE Leakage Detection Systems....................... B 3/4 4-la Operational Leakage............................. B 3/4 4-2 3/4.4.4 CHEMISTRY....................................... B 3/4 4"2 3/4.4.5 SPECIFIC ACTIVITY........'......................, B 3/4 4-3 3/4.4. 6 PRESSURE/TEMPERATURE LIMITS..............,...... B 3/4 4-4
$ )lgIOh 3/4.4.7 HAIN STEAM LINE ISOLATION VALVES................ B 3/4 4-5
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/NISI WASHINGTON NUCLEAR
- UNIT 2 Amendment No. p7,'98
INDEX LIST OF TABLES Continued TABLE PAGE 3.3.4. 2-1 END-OF" CYCLE RECIRCULATIOH PUMP TRIP SYSTEM INSTRUMENTATION...................................... 3/4 3-43
- 3. 3.4.2-2 EHD"OF-CYCLE RECIRCULATION PUMP TRIP SETPGIHTS....... 3/4 3-44
- 3. 3.4. 2-3 END-OF" CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIMES....................................... 3/4 3"45 4.3.4.2.1"1 EHD""F-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS............................ 3/4 3"46
- 3. 3. 5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..................... 3/4 3-48
- 3. 3. 5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS............................ 3/4 3"50 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE(UIREMEHTS............ 3/4 3-51
- 3. 3. 6-1 CONTROL ROD BLOCK IHSTRUMENTATION.................... 3/4 3-53
- 3. 3. 6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS........... 3/4 3"55
- 4. 3. 6" 1 CONTROL ROD BLOCK INSTRUMENTATIOH SURVEILLAHCE Rf(UIREMENTS...,........ 3/4 3-56
- 3. 3. 7. 1-1 RADIATION MONITORING INSTRUMENTATION................. 3/4 3-59
- 4. 3. 7. 1-1 RADIATIQN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............,,.......,..... 3/4 3-60
- 3. 3. 7. 3-1 METEOROLOGICAL MONITORING INSTRUMENTATION............ 3/4 3-65
- 4. 3. 7. 3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................. 3/4 3-66
- 3. 3. 7. 4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION........... 3/4 3-68
- 4. 3. 7. 4" 1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLAHCE REQUIREMENTS 3/4 3-69 WASHINGTON NUCLEAR " UNIT 2 XX11
I CONTROLLED COPY STRUMENTATION SEI IC MONITORING INSTRUMENTATION LIMITI CONOITION FOR OPERATION 3.3.7.2 Th seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPE BLE.
APPLICABIlITY: t all times.
ACTION:
'a 0 With one or more of the above required seismic monitoring instruments inoperable f more than 30 days, in lieu of any other report required by Specificats n 6.9. 1, prepare and submit a Special Report to the Commission purs ant to Specification 6.9.2 within the next 10 days outlining the ca e of the malfunction and the plans for restoring the instrument(s) o OPERABLE status.
- b. The provisions of Spe ifications 3.0.3 and 3.0.4 are not applicable.
SURYEILLANCE RE JIREMENTS 4;3.7.2. 1 Each of the above required sei ic monitoring instruments shall be demonstrated OPERABLE by the performance o the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST, and CHANNEL CALIBRATION operati s at the frequencies shown in Table 4.3.7.2-1.
4.3.7.2.2 Each of the above required seismic mo toring instruments actuated during a seismic event greater than or equal to 0. 1 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIB TION pe~formed within 5 days following the seismic event. Oata shall be re rieved from actuated instruments and analyzed to determine the magnitude'of the vibratory ground motion. In lieu of any other report requi~ed by Specifi ation 6.9.1, a Special.
Report shall be prepared and submitted to the Commission ursuant to Specifi-cation 6.9.2 within 10 days describing the magnitude, freq ncy spec rum, and resultant effect upon unit features important to safety.
WASHINGTON NUCLEAR " UNIT 2 3/4 3-61
TABLE 3. 3. 7. 2" 1'EISMI C MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS INSTR ENTS AND SENSOR LOCATIONS RANGE OPERABLE
- 1. Tri ial Tim'e-History Accelerographs
- a. R ctor Building foundation +1g
- b. Con ainment Orywell floor +1g
- c. Free ield +lg
- 2. Triaxial Pea Accelerographs
- a. Reactor ve el head +Sg
- b. HPCS injects n piping ~5g
- c. Standby servi water pump house +5g
- 3. Triaxial Seismic Swit es
- a. Reactor Building fo dation 0.025g to 0.25g 1(a)
- 4. Triaxial Response-Spectrum ecorders
- a. Reactor Building floor 1.6g to 34g 1(a)
- b. HPCS injection line piping upport 1.6g to 34g 1 C. Reactor Building refueling oor 1.6g to 34g 1
- d. Radwaste Building foundation 1.6g to 34g 1 (a)With reactor control room annunciation.
WASHINGTON NUCLEAR - UNIT 2 3/4 3"62
CONTROLLED COPY TABLE 4.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL INSTRUMENTS NO SENSOR LOCATIONS 'HECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION
- 1. Triaxial me-History Accel erographs
- a. Reactor uilding foundation SA
- b. Containm t Drywell floor SA
- c. Free fiel SA
- 2. Tri axial Peak Acc erographs
- a. Reactor vessel ad N.A. N.A.
- b. HPCS injection ps ing N.A. N.A.
C. Standby service wa er pump house N.A. N.A.
- 3. Triaxial Seismic Switches
- a. Reactor Building foundatl n M(a) SA
- 4. Tri axial Response-Spectrum Recor rs
- a. Reactor Building floor SA
- b. HPCS in jecti on l ine pi ping support N. N.A.
C. Reactor Building refueling floor N. A. N.A.
d, Radwaste Building foundation N.A. N.A.
(a)Except seismic trigger.
MASHINGTON NUCLEAR - UNIT 2 3/4 3"63
CONTROLI.ED COPY INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Conti nued) 3/4. 3.7. 2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those. features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12, "Instrumentation for Earthquakes," April 1974.
3/4.3.7. 3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February, 1972.
3/4.3.?. 4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of Appendix A to 10 CFR Part 50.
3/4.3.7. 5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0737,
" " "Clarificat on of TMI Action Plan Requirements," November 1980 jgp~p~< pop ~JJJ ~y
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3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
WASHINGTON NUCLEAR - UNIT 2 B 3/4 3-5 Amendment No. Sl, 98
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