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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
WGNTBOILLF.D "CO -,;
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION PAGE'/4 3/4. 3 INSTRUMENTATION 3/4. 3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3-1 3/4. 3. 2 ISOLATION ACTUATION INSTRUMENTATION. 3/4 3-10 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION .. 3/4 3"25 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION S..
ATMS Recirculation Pump Trip System Instrumentat ion.. 3/4 3-37 End-of-Cycle Recirculation Pump Trip System Instrumentation.. 3/4'3"41 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEH 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 Seismic Monitoring Instrumentation..;-.... ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-61
., Meteorological Monitoring Instrumentation............ 3/4 3"64 Remote Shutdown Monitoring Instrumentation........... 3/4 3-67 Accident Monitoring Instrumentation...... 3/4 3-70 P
Source Range Monitors. 3/4 3-76 Traversing In-Core Probe Sy'tem 3/4 3-77 Fire Detection Instrumentation. 3/4 3-79 Loose-Part Detection System. 3/4 3"83 Radioactive Liquid Effluent Monitoring 0 o'p)A Instrumentation...................... 3/4 3"84 Radioactive Gaseous Effluent Monitoring
'OO.
<0 OO
<A Instrumentation.. 3/4 3-89 IO OX 3/4. 3. 8 TURBINE OVERSPEED PROTECTION SYSTEM. 3/4 3-96 CUO HQ OA LDLL 3/4.3.9 FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION... 3/4 3"98 Oo:
QQ RG.O.
3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION............... 3/4 3-102 WASHINGTON NUCLEAR - UNIT 2 Vl Amendment No. 16
BASES SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............ 8 3/4 3-4 Seismic Monitoring Instrumentation.............. 3/4 3"4 Meteorological Monitoring Instrumentation....... 8 3/4 3-5 Remote Shutdown Monitoring Instrumentation...... 3/4 3-5 Accident Monitoring Instrumentation............. 8 3/4 3"5 Source Range Monitors........................... 8 3/4 3"5 Traversing In-Core Probe System................. 8 3/4 3"5 Fire Detection Instrumentation.................. 8 3/4 3"6 Loose-Part Detection System..... 8 3/4 3."6 Radioactive Liquid Effluent Monitoring Instrumentation... 8 3/4 3-6 Radi oacti ve Gaseous Effluent Monitoring Instrumentation................ 8 3/4 3-7 3/4. 3. 8 TURBINE OVERSPEED PROTECTION SYSTEM............. 8 3/4 3"7 3/4. 3. 9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATIOH IHSTRUMENTATIOH...... 8 3/4 3"7 3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION......... 8 3/4 3"7 3/4.4 REACTOR COOLANT SYSTEM 3/4. 4. 1 RECIRCULATION SYSTEM......... 8 3/4 4-1 3/4. 4. 2 SAFETY/RELIEF VALVES...........,........,,....... 8 3/4 4"1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...... 8 3/4 4"2 Operational Leakage . 8 3/4 4"2 3/4. 4. 4 CHEMISTRY..... 8 3/4 4-2 3/4. 4. 5 SPECIFIC ACTIVITY. 8 3/4 4-3 3/4. 4. 6 PRESSURE/TEMPERATURE LIMITS..................... 8 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 8 3/4 4"5 WASHINGTON NUCLEAR - UNIT 2 X111 Amendment Ho. 16
STRUHENTATION CHL INE DETECTION SYSTEM LIHITI CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detection system subsystems shall e OPERABLE" wit their alarm/trip setpoints adjusted to actuate at a hlorine concentration o less than or equal to 5 ppm within 10 seconds.
APPLICABILITY: Al OPERATIONAL CONDITIONS.
ACTION:
'a ~ Mith one chlor e detection subsystem inoper le, restore the inoperable detec ion subsystem to OPERABLE atus within 7 days or, within the next 6 ours, initiate and mai ain operation of at least one control room em rgency filtration s tern train in the isolation mode of operation.
Mith both chlorine dete ion subsy ems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain ope tion o at least one control room emer-gency filtration system tra'n i the isolation mode of operation.
C. The provisions of Specifica o 3.0.4 are not applicable.
I SURVEILLANCE REOUIREhlENTS 4.3.7.8 Each of the abov required chlorine detect n system subsystems shall be demonstrated OPERABL by performance of
- a. CHANNEL C CK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.. CHANNE FUNCTIONAL TEST at least once per 31 days, and
- c. CH <EL CALIBRATION at least once per 18 months.
"The ormal or emergency power source may be inoperable in OPERATIONAL CO ITION 4 or 5.
MASHINGTON NUCLEAR - UNiT 2 3/4 3-78
t 4
PLANT SYSTEMS SURVEILLANCE REOUIREMEHTS Continued "la Co At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painti.ng, fire, or chemical release in any ventilation zone cormunicating with the train by:
- 1. Verifying that the train satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05 and uses the test procedure guidance in Regulatory
'ositions C.5. a, C.5.c, and C.5. d of Regulatory Guide 1. 2, Revision 2, March 1978 when operating at a flow rate of 1000 cfm + lOX.
- 2. Verifying within 31 days after removal that a laboratory analysis of. a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory- Guide 1.52, Revision 2, March 1978, meets the laboratory tes'ting criteria of R ulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, g h 1978, for a methyl iodide penetration of less than 1.0"; aalu
- 3. Yerifying a tras w rate of 1000 cfm + 10 during train operation when test 'n accordance with ANSI H510-1980.
- d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of c a 1 adsorber operation by verifying
~
within 31 days after remova sentative carbon sample obtai
~ a n
laboratory analysis of a repre-accordance with Regulatory Positon C.6.b of Regulatory Gui 52, Revision 2, March 1978, meets the laboratory testing crit of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision arch 1978, for a methyl iodide. penetration of less than l. 0 .
- e. At least once per 18 months by:
- l. Yerifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches water gauge while operating the train at a flow rate of 1000 cfm + 10 .
4 4
NSHIHGTON NUCLEAR - UNIT 2 3/4 7"6
'PLANT SYSTEMS SURVEILLANCE REOUIREMENTS Continued)
Verifying that on each of the below pressurization mode actuation test signals, the train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch water gauge relative to the outside atmosphere during train operation at a flow rate less than or equal to 1000 cfm:
a) Drywell pressure-high, b) -Reactor vessel water level-low, and c) Reactor Suilding exhaust plenum-high radiation.
Verifying that the heaters dissipate 5.0 + 0.5 kW when tested in accordance with ANSI sV510-1980.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter 'bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05X in accordance with ANSI N510=1980 whi le operating the train at a flow rate of 1000 cfm + 10'~.
After each complete or<par. ial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration~an+ bypass leakage testing acceptance, criteria of less than 0.05K~'i'ccordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the train at'a flow rate of 1000 cfrii<+~10~.
'plASHINQTON iVUCLEAR
- UiVIT 2 3/4 7-7
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 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 'o 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, "Qnsite Meteorological Programs," February, l972.
3/4.3.7.4 REMOTE SHUTDOWN MONITORING IHSTRUMENTATION 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 fo: Light Water Cooled Nuclear Power Plants to 'As'sess Plant Conditions During and Following an Accident," December 1975,and NUREG-0737, "Clarification c" TMI Action Plan Requirements," November+1980.
3/4.3.7.6 SOURCE RANGE MONITORS+w The source range monitors provide the operator with information o'he 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 IH"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.
- 4. 3. 7. 8 CHLORINE DETECTION SYSTEM The ILITY of the chlorine detection system ensures that an acc chlorine release w detected promptly and the necessary r ie actions will be automatically init> to provide protection f ntrol room person-nel. Upon detection of a high conce ion o rine, the control, room emergency ventilation system will au a laced in the isolation mode of operation to provide the red protection. Tne ion systems required by this speci ficati e consistent with the recommendations o u Iatorv otection of Nuclear Power Plant Control Room Operators a ccidental Chlorine Release," February 1975.
WASHINGTON NUCLEAR
- UNIT 2 B 3/4 3-5
V I
~ I f
4