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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
~ ~
n n u)g PhfA . LL WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLAXT PRO(;ED t. RES il:DL;'IIL m'h p-PROCEOURE NUMBER APPR EO OATE
<<12e10.5 06/21/83 VOLUME NAME 12 CHEMIS. RY PROCEDURES SECTION 12.10 POST ACCIDENT SAMPLING PROCEDURES TITLE "12.10.5 GAS SAMPLE ANALYSIS 12.10.5.1 P~ur oee This procedure determines gas concentrations and activity from a sample taken from the post accident sample station.
12.10.5.2 Precautions/Prere uisites A. Lab personnel shall be issued extremity dosimetry as per Health Physics policy.
B. Lead shielding must be setup prior to sample handling.
C. The gamma spectrometer system must be operable.
D. The gas chromatograph must be calibrated (see 12.10.5.5) prior to analysis.
E. The gas chromatograph must be operating 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to analysis.
F. Carrier gas flow must be approximately 20cc/min (20 psi).
G. All sample handling must be carried out in a hood.
H. Appropriate dose rate meter must be available and in calibration.
Use continuously to assure exposure ALARA.
12.10.5.5 E~ui ment A. 1.0 ml and 0.1 ml gas tight syringes B. Oxygen, hydrogen and nitrogen gas standards C. 14 ml and 125 ml serum vials 8307080i68 830623 PROCEOURE NUMBER REVISION NUMBER PDR ADOCK 08000397 PAGE NUMBER h
PDR j 12.10.5 12.10.5-1 of 8 WP 597 R1
0 I GHJ iQHTYiGQRU
,(i,">
, 12.10.5.4 Procedure A.. On HP3390 integrator enter scale setting:
- l. OP ( ) 6
- 2. Scale setting B. Open valve on gas tight syringe.
C. Insert 1.0 ml syringe needle into sample part and withdraw syringe plunger to 1.0 ml.
D. Allow a few seconds for pressure to equalized across the needle.
E. Close valve on syringe and release plunger.
F. Note actual volume sampled and record on. Attachment I.
G. Withdraw syringe from sample.
H. Insert syringe into septum on the gas chromatograph.
Open valve on syringe and inject sample.
If not already depressed, press the AUTO button then press clear.
Read percent concentration from HP3390 integrator and calculate 1 .1 .5.
A.
~1 percent concentration in containment as per Attachment I.
From sample dose rate determine what dilutions are needed to reduce sample dose rate to less than 5 mrem at 2 inches. Record dilutions on Data sheet, Attachment III.
B. Place septums or appropriate number of serum vials and evacuate.
C. Place vials behind lead shielding.
D. .With an appropriate syringe inject a volume of H20 equal to the desired aliquot then withdraw an aliquot and transfer to a 14 ml or 125 ml serum vial.
E. Complete required dilutions behind the lead shield as planned.
Final dilution is into a 14 ml serum vial for counting.
RQCEDURE NUMBER REVISION NUMBER PAGE NUMBER W~QB
,12.10.5 0 12.10.5-2 of 8
Bag or wrap in plastic the .final dilution, smear and survey'then when less than 1000 dpm/100cm2 contamination, remove to counting room.
G. Adjust sample counting time to reflect its activity as .estimated by its dose rate.
12.10.5.6 Calibration A. Using a gas tight syringe obtain a 100 micro liter sample of standard hydrogen gas.
B. Inject into gas chromatograph.
C. If not already depressed, press AUTO.
D. Press CLEAR.
E. When chromatogram is complete enter the data into the HP3390 integrator:
- 1. Del CALIB
- 2. CALIB ESTD
- 3. Ref RTW = 5
- 4. RTW = 5
- 5. RT = (retension time for hydrogen)
- 6. AMT = 10.0 (10.0 vol percent)
P
- 7. ENTER F. Repeat Steps 12.10.5.5.A through 12.10.5.5.D for oxygen gas standard.
G. Enter data into HP3390 integrator:
- l. EDIT CA! IB
- 2. REF'RTW = 5
- 3. RTW =5
- 4. CAL8 = 2
- 5. RT = (retension time for oxygen)
ROCEDURE NUMBER REVISION NUMBER )PAGE NUMBER 12.10.5 0 I 12.10.5-3 of 8 W~90
- 6. AMT = 10. (volume percent) 7.. AMT/HT = (10.0 volume percent divided by peak height)
- 8. ENTER H. Repeat Steps 12.10.5.5.A through 12.10.5.5.D for nitrogen.
I. Enter data into HP3390 integrator:
- l. EDIT Calib
- 2. REF RTW = 5 RTW = 5
- 4. CALO = 3
- 5. RT = (retension time for nitrogen)
- 6. AMT = 10.0 (volume percent nitrogen)
- 7. AMT/HT = (10.0 volume percent divided by peak height)
- 8. ENTER Steps 12.10.5.5.A through 12.10.5.5.D can be repeated for any additional gases.
If a calibration table already exists, the calibration table can be updated by injection of a standard as in Steps 12.10.5.5.A through 12.10.5.5.D then pressing RCAL. This process would have to be repeated for each gas unless a mixed gas standard is available.
12.10.5.7 Documents A. Attachment I, Calculation of Containment Gas Concentration B. Attachment II, Conversion Factors C. Attachment III, Dilution Data Attachment IV, Final Concentration Calculation PROCEDURE hlUM8KR REVISION IYUM8ER ~PaCa nUM88R W~Qa 12.10.5 0 l 12.10.5-4 of 8
0' Sample percent by volume t
Calculation of Containment Gas concentration of each gas:
~
Concentration
~
'A VS A = AT V
A Where:
AT = volum percent analyzed AS = volum percent in vial before analysis VA = volume of aliquot removed from standard VS = volume of vial Percent by volume of each gas in containment:
C
( s)( c)( v) pc (Containment Pressure) (Partial Pressure of Water)
TV Vial Temperature Vial Pressure mm Hg TC Containment Temp Containment concentration in percent by volume = X H2 Attachment I ROCEOURK NUM8KR [REVISION NUM8ER PAGE NUMBER W~94 12.10.5 ~
0 !
12.10.5-5 of 8
L 0 Conversion Factors ounds/s uare inch to mm H d
11/'4.696 1b/in Fto C oF = 9/5 (oC + 32)
Cto K oK =oC+ 273 Attachment II PROCKQVRK NVMBKR iRKVtStON aVM8KR [PACK i>VM8KR W~94 12.10.5 0 I 12.10.5-6 of 8
~>
, Dilution 1 aliquot cc (a) final volume cc (b)
Dilution 2 aliquot cc (c) final volume cc (d)
Dilution 3 aliquot cc (e) final volume cc (f) b X
d f X = dilution factor (df) a c e (measured uCi/cc)(df) = AR, activity remaining in vial after gas chromotgraphy analysis i
A. =
VA + VS VS A
R Ai = initial uCi/cc in sample VA=l CC VS = volum of vial Attachment III RQCEDVRE NUMBER REVISION NVMBER iPAGE NVMBER whee 12.10.5 0 12.10.5-7 of 8
~
~
'I Final Concentration I~ecto e. uCI/co 'A UC1/CC kr85 kr88 Xe-133 Xe-135 Attachment IV PROCEQURE NUMBER (REVISION NUMBER (PAGE NUMBER wanga 12 10 ~ 5 I 0 12.10.5-8 of 8
