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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. 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 ML17291B1621995-03-0606 March 1995 Rev 9 to Procedure Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii. ML17291A1341994-06-16016 June 1994 Pages 9 & 10 to Rev 11 to PPM 13.12.15,inadvertently Omitted from Original Submittal ML17291A6661994-04-30030 April 1994 WNP-2 Odcm. ML17290A9951993-12-31031 December 1993 Amend 16 to Odcm. ML17290A3771993-05-27027 May 1993 Amend 1 to Inservice Insp Program Plan,First Insp Interval. New Relief Request Will Be Submitted to Define Areas of Limited Exam of RPV nozzle-to-shell Welds ML17272B0141993-04-28028 April 1993 Amend 1 to Vols 1-3 of ISI Program Plan. ML17289B2621993-02-22022 February 1993 Rev 1 to LTI7.4, Operations Liaison Responsibilities. ML17289B1931993-01-31031 January 1993 Offsite Dose Calculation Manual. ML17289A7811992-07-31031 July 1992 Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties. ML20097H7511992-04-23023 April 1992 Plant Procedure 10.25.89, One Hour - Three Hour Fire Barrier Installation ML17289A5031992-04-0101 April 1992 Washington Nuclear Plant - 2 Licensed Operator Requalification Program Corrective Action Plan Resolution Documentation. ML17286B1791991-11-21021 November 1991 Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2. ML17286A9051991-06-28028 June 1991 Odcm. ML17286A7381991-04-30030 April 1991 Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15 ML17286A4971990-12-0505 December 1990 Revised Epips,Including Rev 8 to 13.8.2,Rev 10 to 13.10.9, Rev 8 to 13.11.13,Rev 8 to 13.14.1,Rev 6 to 13.14.3,Rev 10 to 13.14.4 & Rev 7 to 13.14.9 ML17285B0621990-02-26026 February 1990 Amend 7 to Odcm. ML17285B0501990-02-22022 February 1990 Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr ML20066K0451989-03-28028 March 1989 Rev 5 to Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii ML17285A2621988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML17285A2511988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML20090M2951987-11-17017 November 1987 Rev 4 to FATE-84-100, Vipre Code Maint Procedures Manual ML20236N3071987-11-0606 November 1987 Corrected Page 16 of Rev 7 to Procedure 13.14.2, Process for Determining Protective Action Recommendations & Protective Action Decisions ML17279A5931987-10-0808 October 1987 Rev 3b to Pump & Valve Inservice Test Program Plan. ML17284A3901987-06-30030 June 1987 Draft A-3453-87-6, Washington Nuclear Plant 2 Generic PRA- Based Insp Plan. ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency). ML20215B7551986-07-24024 July 1986 Rev 3 to NDE & I Instruction Qci 6-4, Ultrasonic Exam BWR Nozzle Inner Radius ML20215B7631986-03-20020 March 1986 Rev 3 to NDE & I Instruction Qci 6-13, Ultrasonic Exam of Piping Welds (Manual) ML17278A5681986-01-0606 January 1986 Rev 5 to Emergency Plan Implementing Procedure 13.14.7, Emergency Training. ML17278A5341985-12-20020 December 1985 Rev 3a to Pump & Valve Inservice Test Program Plan. ML17278A4731985-11-0101 November 1985 Revised Emergency Procedures,Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions, Rev 0 to Procedure 5.0.1, Emergency Operating Procedure Flow Chart & Rev 1 to Procedure 5.1.3, Reactor Power Control. ML17278A5491985-09-24024 September 1985 Rev 0 to Procedure Tp 8.6.6, Special Test Procedure for Tdas Class 1E Isolators. ML20133N3611985-09-0909 September 1985 WPPSS-2 Emergency Preparedness Exercise Manual for 850909-13 ML20129B5491985-05-0606 May 1985 Vol 1 of Rev 0 to Inservice Insp Program Plan ML17278A4291985-03-20020 March 1985 Rev 1 to Operating & Engineering Test Procedure 8.2.92, UHS Performance. ML17277B6461985-03-0505 March 1985 Amend 4 to 85-01, Preservice Insp Program Plan, Vols 1-4 ML17277B3101984-02-29029 February 1984 Control Room Design Review Program Plan. ML17277B3091984-02-17017 February 1984 Function & Task Analysis of Emergency Operating Procedures. ML17277B7331983-12-28028 December 1983 Rev 2 to 23A1900AA, RHR Sys. ML17277B0401983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.3.8, Equipment Clearance & Tagging. ML17277B0421983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.5.1, Tech Spec Surveillance Testing Program. ML17277B0361983-11-0707 November 1983 Rev 5 to Administrative Procedure 1.3.1, Standing Orders/ Night Orders. 1999-08-27
[Table view] |
Text
FRQCEQURE REVISION FQRM eORtQiNAL Procedure Nunber: T 8 b Current Revision: 0 Procedure
Title:
6 c.iaI Hei P~ek~l- 4r T C a.zg iE. ZMlcrtarS POC Meeting Nuober:
CHANGE: (See attaclled copy of'arked up procedure.)
JIVE.LE'T E' fafoc.a C vfEE. 8601060086 851220 PDR ADOCK 0>000~97 REASON FOR CHANGE: F PBR.
~+ST C.n~ P~ea Yes No This procedure/revision constitutes a change to procedures as described in the FSPR.
- 2. x This procedure/revision constitutes 'a change to Technical Specif ications.
This pzoceduze/revision constitutes an unreviewed safety ques-tion as defined in 10CFR50.59. 3ustification for this evalua-tiOn'Aay i'OCC+rg /)CS hC fCV'f CMCd + liay I W 3CPI e Sl/ Iafff r/ i'~ t OCR 4. $
' rare. ~j dE
+ re VAC 7 w~.
- 4. P This procedure/revisi:on constitut s an unreviewed environmental question or a charge--in the Environmental Protection Plan.
(See Tech. Spec. App;-B, EPP 3.0.)
5, p' This procedure/revision nullifies a previous regulatory commitment being qatisfied. (See paragraph =1.2.4.2.A.2.d.}
Stlppir4 in+Os ~~~ S~+ W lVIPC Cj>UCgkr'>M A. 'S~Oaf W4*l
- 6. This procedure revision constitutes a %el<-8V-S3V QZ. 3~><
<c.aQ.oEZ Verafxed y Oate TP 8.6.6 TP 8.6.6-2 of 5
p kl J
~
I
B. Provide test signals on the recorder to verify the voltage scale.
Label the signals and the voltage ranges on the recorder trace.
g go-F5 Ver fied by Date C. Mount the isolator to be tested in an isolator tray and electrically connect it as shown in Figure 1. Provide a 4 ma signal (1 VOC across Rl) frcm the diff'erential pressure transmitter. Record the serial number of the isolator.
Isolator S.N. 57% g-z.o Q=/o Verif'ied by Date CAUTION: The perf'ormance of the next step will have an unknown eff'ect on the isolator. Care should be taken to insure- no personnel harm free any resultant action.
O. Turn on the visicorder at 40 mn/sec and turn on switch Sl. After approximately 3 seconds, turn switch Sl to the "OFF" position.
g- zw-8a Verii'ied by Date Sign and date the recorder trace and identify aU. signals and the isolator serial rubber. Attach the trace to= this procedure.
'-z;o-FS Yerxfied by , Date Repeat Steps C through E'bove for two more isolators chosen at random. Record their serial numbers below.
g-z.o -F<
so ator S. . er ed by Date G. For all three cases above, determine:
- 1. The voltage applied to the output.
- 2. The length of time voltage was appU.ed.
- 3. The maxifmm voltage resulting on the input.
- 4. The duration of the voltage resulting on the input.
Surearize the results in Section 8.6.6.7.
f-z, o-7S era red by Date TP 8.6.6 TP 8.6.6-3 of 5
I" H. Compare the results of this test to the acceptance criteria 8.6.6.6 and verify that the isolator f'unctioned properly.
of'ection Gr ~
9-ac -F<
Criteria Dj'.6.6.6 Acce tance A. Electrical The Class 3E signal masured interference is less than 50 mv peak to peak f'r ra more than 10 msec during the application of'he Maximun Credible Fault Voltage and the signal f'unction is not inhibited.
The Class IE, signal maintains its initial'alue af'ter the Haximun Credible Fault Voltage has been removed (within signal tolerance transmitter).
of'he B. P sical Acce tance Criteria The isolator remains intact during and af'ter the application of the Haximun Credible Fault Voltage.
7.6. ~ .7 ~Tt S TP 8.6.6 TP 8.6.6-4 of'
T TP 8.6.6 TEST
SUMMARY
STEP B. The signals recorded and voltage ranges are INITIAL CH DESCR IPT ION VALUE SENSI T I V ITY 1 Isolator Power Supply 24. 01VDC 4. 03VDC/DIV 2 Isolator Input 1. 02VDC . 05VDC/DIV 3 Transmitter Power Supply 24. OOVDC 3. 51VDC/DI V 4 Isolator Output 10. 22VDC 34. OVDC/DIV STEP C. The functionality of the isolator (measuring of the output voltage) was also veri Fi ed in this step.
STEP D. The actual chart speeds for Test Case ¹1 and ¹2 were 40 in/sec and For Test Case ¹3 80 in/sec.
STEP G. From the attached recorder traces:
TEST OUTPUT MAXIMUM CASE¹ VOLTAGE DURAT I ON VOLTAGE DURATION 1 114. 6Vrms >3 Sec. .0. 070VDC(p-p) 250usec.
2 3
114. 6Vrms 114. 6Vrms
>3 Sec.
>3 Sec. '.
..0, 275VDC(p-p) 400VDC(p-p )
250usec.
250usec.
STEP H. The resultant voltage spik'es on the input (Class 1E) side oF the i solator exceeded the acceptance criteria voltages oF Section 8 6. 6. However> the pulse duration was much shorter than the maximum allo~ed. The: control signai was not affected (other than the pulse) and the transmitter con-tinued its function aFter the application of the voltage.
The isolator in < all three cases) performed its intended Function bg not allotting the Maximum Credible Fault voltage to adversity affect the Class 1E Function.
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