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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
ELECTRICAL POWER SYSTEMS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITIHG CONDITION FOR OPERATION 3.8.4.2 All primary containment penetration conductor overcurr ent protective devices shown in Table 3.8.4.2-1 shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
- a. With one or more of the primary containment penetration conductor overcurrent protective devices-shown in Table 3.8.4.2-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION r ~
statement for the affected system and:
- 1. For 6. 9 kV circuit breakers, de-energize the 6. 9 kV circuit(s) by tripping the associated redundant circuit breaker(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,gnd verify the redundant circuit breaker to be tripped at leastlgoce per 7 days thereafter.
- 2. For 480 voTtgcircuit breakers, remove the inoperable circuit breaker(s) from~ service, by removing the fuses within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the~fuses associated with the inoperable breaker(s) to be removed at~+least once per 7 days thereafter.
Otherwise, be in at least>HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within theh following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
kb:~W
- b. The provisions of Specification 3.0.4 are not applicable to over-current devices in 6.9 kV circuits which have their redundant circuit breakers tripped or to 480 volt~circuits which have the fuses asso" ciated with the inoperable circuisti breaker removed.
SURVEILLANCE REQUIREMENTS
- 4. 8. 4. 2 Each of the primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.2-1 shall be demonstrated OPERABLE:
- a. At least once per 18 months:
- 1. By verifying that the medium voltage, 6. 9 kV, circuit br eakers are OPERABLE by selecting, on a rotating basis, at least lOX of the circuit breakers of each voltage level and performing:
a) A CHANNEL CALIBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuits function as designed.
c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10~ of all the circuit breakers of the inoperable type -shall also be functionally tested until no more failures are found or all circuit breakers of. that type
,have been functionally tested.
WASHINGTON NUCLEAR - UNIT 2 3/4 8"21 8506260381 8506i3 PDR ADOCK 05000397 P PDR
ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS Continued
- 2. By selecting and functionally testing a representative sample of at least 10Ã of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis. Testing of these circuit breakers shall consist of injecting a current with a value equal to 300Ã of the pickup of the longtime delay trip element and 150K of the pickup of the short time delay trip element, and verifying that the circuit breaker operates within the time delay band-width for that current specified by the manufacturer. The instantaneous element shall be tested by injecting a current equal to &OX of the pickup value of the element and verifying that the'circuit breaker trips instantaneously with no inten-tional time delay. Molded case~~cbcuit breaker testing shall also follow this procedure.except that generally no more than two trip elements, time delay>'and instantaneous, will be involved. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each ci,pcugt breaker found inoperable during these functional tests. ~ay additional representative sample of at least 10Ã of all .thegeircuit breakers of the inoperable type shall also be functionilly tested until no more failures are found or all circuit+breakers of that type have been functionally tested>
each type~o fuse on a rotating basis. Each represe sve sam f fuses shall include at least 10~ of all es of that type. The tional test shall consist of on-destructive resistance measur test which de rates that the fuse meets its manufacturer s i eria. Fuses found inoper able during these functi OPERABLE fuses pri ,
t 'hall o resuming oper
' be replaced with For each fuse found inoper during these functional tes an additional repres ive sample of at least 10Ã of all fuses hat type .
be functionally tested until no more failures are
- b. At least once per 60 months by subjecting each .cir cuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
WASHINGTON NUCLEAR " UNIT 2 3/4 8-22
~ 1 TABLE 3.8:4.2-1 PRIHARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES EQUI PMENT PRIMARY PROTECTION BACKUP PROTECTION 5900V Circuit Breakers
~ RRC-P-1A E-CB-RRA (Relay) E-CB-S5 (Relay) E-CB-t~2/5 (Relav)
RRC-P-18 E-CB-RRB (Relay) E-CB-S6 (Relav) E-CB-N2/6 (Relay)
- b. 480VAC Fused Disconnects i
C-V-72A HC-7C 1.125AF t 258 RC V-728 MiC-8C 1.25AF MC-8C F RCC- 7A MC-7C 1.125AF h'C-7C 25AF CRA-FN- -2 t'iC-88 r&
' 110AF 1C-88 200AF RRC-V-678 hiC-8C 25AF MC- 90AF RRC-V-238 MC-SC 15AF H SC 25AF
. Rb.'CU-V-102 hiC-SC 5AF C-8C 25AF RHCU- V-106 HC-SC 3AF H C-SC 25AF RRC-V-23A C-SC 4,1AF h 1C-8C 25AF RMCU-V>>101 RMCU-V>>100 RCC-V-178 RCC-V-71C RCC-V-718 M
MC-p'c-7C HC-SC MC-8C MC-8C C 43A FA 1."25)F 1.25AF 1.25AF,.
MC-8C t 1C-SC hi C-8C H C-8C MC-8C
~
25AF 25AF 25AF 25AF 25AF CRA-FN-1A-2 HC-78 iOOAF @~i "iC-78 200AF CRA-FN-1A-1 MC- iC;78 200AF CRA-FN-2A-2 P -78 60A MC~78 90AF CRA-FN-2A-1 C-78 150AF MC-78 300AF HC-78 25AF M C-78 50AF CRA-FN-5A'RA-FN-4A HC.-78 15AF -78 50AF CRA-FN-5C HC-78 25AF t lc- 50AF
. CRA-FN-3A HC-78 25AF MC-78 50AF CRA-FN- -2 t"C-88 100AF M C-SB 200AF CRA-F '-18-1 t<C-88 100AF . MC-88 OAF CP, N-1C-1 HC-88 100AF 1C-88 20
".,A-Fil-28-1 HC-SB 15GAF MC-88 F,'00A h>>
'i
'I HiS-V-16 i".'iCU-V-1 HiC-88-A F~ed ~m
~d4"-
125AC8 HiC-SB-A t1C-88 125ACB RHR Vc t'.C-88-A m+F'lC-88 I'iC-88 125 ACB RCiC-V-63 tiC-88-A tlC-88 125ACB oCr-1t-40 i4iC-88-A MiC-88 '125ACS
.-",I'.=.-V-:238 t'iC-88-A t~c-88 12= ACB riC .C- ii -/c tlC-88>>A t 1C-88 125ACB r ~
~
~ rl
- ."-. ~ "; '"". Or t'uc1 ea. - h'n 1 . ~/>> A
- ";~end
- ,,en'o. 6
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EQUIPHEN7 PRIMARY. PROTECTION BACVUP PROTECTION CRA- HC-8B 25AF HC- OAF CRA-FN-3C HC-SB 25AF -SB 50AF CRA-FN-4B Yi- F HC-SB 25AF t'.S-V-1 C-SC-B 1AF -SC-B 25AF IRS-'! ac-SC-B 1AF HC F RHR-V-123A Y)C-SB-A ~%AF- HC-8B 125ACB f~ A
'.-.:-: '.--,-;On Nuclear - Un'.- ":
3/< B-24
0 v I
ql V
ELECTRICAL POWER SYSTEMS BASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE OEVICES Primary containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
The surveillance requirements applicable to lower voltage circuit breakers cad-4usac provide)'ssurance of breaker ai4-A~ reliability by testing at least one representative sample of each manufacturers brand of circuit breaker. andM~
Each manufacturer's molded case and metal case circuit breakers ~W~
are grouped into repgesentative samples which are thorn tested on a rotating treat each group as a separate~type of breaker ar-~us-for surveillance purposes.
The bypassing of the Pm motor~opgeated valve thermal overload protection continuously or during accident condjtions ensures that the thermal over load protection will not prevent safety-,, elated valves from performing their function. The surveillance requirements for demonstrating the'bypassing of the thermal overload protection continuously and during accident conditions are in accordance with Regulatory Guide 1.106 "Thermal Overload Protection for Electric Motors on Motor Operated Valves,/~Revision 1, March 1977.
@~5 WASHINGTON NUCLEAR - UNIT 2 B. 3/4. 8-3
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