Rev 3 to Inservice Test Program ISI-P-008, Summary of ChangesML20151R033 |
Person / Time |
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Site: |
Vogtle |
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Issue date: |
04/13/1988 |
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From: |
GEORGIA POWER CO. |
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To: |
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Shared Package |
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ML20151H972 |
List: |
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References |
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ISI-P-008, ISI-P-8, NUDOCS 8804270220 |
Download: ML20151R033 (8) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program. ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program. ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program. ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20091L8331989-05-19019 May 1989 Rev 0 to Corporate Guidelines 1.1.2, Positive Discipline ML20246N6241989-05-10010 May 1989 Rev 3 to Vogtle Electric Generating Plant Unit 1 Inservice Insp Program ML20078A5401988-11-15015 November 1988 Updated Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20195J9191988-11-11011 November 1988 Rev 4 to ISI-P-010, Preservice Insp Program Vogtle Electric Generating Plant Unit 2 ML20196B1551988-10-25025 October 1988 Rev 0 to ISI-P-014, Inservice Insp Program ML20195B3901988-10-18018 October 1988 Aw Vogtle Simulator Certification Plan ML20091L8931988-10-0303 October 1988 Voided Rev 9 to Procedure 10000-C, Conduct of Operations ML20155C0751988-09-15015 September 1988 Rev 0 to Abnormal Operating Procedures 18038-2, Operation from Remote Shutdown Panels ML20091L8821988-09-0808 September 1988 Voided Rev 10 to Procedure 35110-C, Chemistry Control of Rcs ML20155C0871988-08-19019 August 1988 Rev 9 to Procedure 12006-C, Unit Cooldown to Cold Shutdown ML20151G1851988-07-18018 July 1988 Rev 1 to ISI-P-006, Inservice Insp Program ML20151G1881988-07-18018 July 1988 Rev 2 to ISI-P-006, Inservice Insp Program ML20078A6221988-07-12012 July 1988 Readiness Review Program Module 20 - Instrumentation & Controls ML20078A5931988-06-28028 June 1988 Readiness Review Program Module 13B - Coatings ML20078A5831988-06-22022 June 1988 Readiness Review Program Module 12 - Electrical Cables & Terminations ML20091L7821988-06-0707 June 1988 Rev 0 to Procedure 49006-C, Health Physics & Chemistry Dept Outage Activities Implementing Procedure ML20078A5461988-05-12012 May 1988 Rev 1 to Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20078A5751988-04-13013 April 1988 Readiness Review Program Module 11 - Pipe Stress & Supports ML20151R0331988-04-13013 April 1988 Rev 3 to Inservice Test Program ISI-P-008, Summary of Changes ML20078A6311988-03-16016 March 1988 App F, Inspector Qualification of Vogtle Electric Generating Plant Unit 2 Readiness Review Program ML20148K4301988-03-0202 March 1988 Inservice Test Program 1998-05-25
[Table view] |
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Enclosura Vogtle Electric Generating Plant - Unit 1 Inservice Test Program ISI-P-008 Revision 3 Sumary of Changes Pages 4-22 and 6-35 The progr6m was changed to indicate quarterly testing of valves 1205-HV-8716A and 1205-HV-87168 instead of testing during cold shutdown. Cold Shutdown Justificatic.i CS-35 was also withdrawn.
This change is a result of letter SL-3505 from L.
T. Gucwa (Georgia Power Company) to the U. S.
Nuclear Regulatory Comission.
Pages 4-23 and 6-36 The program was changed to indicate partial stroke testing on a quarterly frequency and full stroke testing during cold shutdown for valves 1205-U6-001 and 1205-05-002. Previously only full stroke testing during cold shutdown was perfonned. Cold Shutdown Justification CS-36 was modified to add partial stroke testing on a quarterly frequency. This change is a result of letter SL-3505 f rom L. T. Gucwa (Georgia Power Company) to the U. S. Nuclear Regulatory Comission.
i Pages 4-25 and 5-26 The spray additive tank vacuum breakers were changed to indicate that they will be tested as safety relief valves instead of quarterly as check valves. Relief Requist RR-26 was also withdrawn. This change was approved by letter dated September 22, 1987 from Ms. M. A. Miller (V. S. Nuclear Regulatory Comission) to J. P.
O'Reilly (Georgia Power Company).
Page 6-37 Cold Shutdown Justification CS-37 wss modified to indicate that flow could circulate to and from the refueling water storage tank to partial stroke exercise valves 1205-U6-009 and 1205-U6-010. This change is a result of letter SL-3505 from L. T. Gucwa (Georgia Power Company) to the U. S. Nuclear Regulatory Comission.
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VLCP Uni t neo. 1 Valve Test List 008 Rtv 3 System: Residual Heat Removal - System Dio. 120$
Sheet I or 2 Ya[ve Relier Valve Clags P&ID Site Act. Req. Or Act. Po Mt_lon or 8tLasker 111 Fr d i Coo rd.1 C_a3 Lih] T,ype Jyp3 16orm f4II Safety Ealb ElTes11_and U El free. C. S. Desc ri p t ion HV 8716A 2 IEy G j Ju k an_d seoEl 1 212 IX4D8122 8 8.00 CA MO O
- At O/C A Y Q Q (F-7) RitR Train A l i Not Leg Isotation
, NV 87168 2 212 IX4D8122 8 8.00 CA MO O Al O/C A Y Q Q (D-7) RHR Tra in 8 l Not leg Isolation HV 8804A 2 212 1X408122 8 8.00 CA MO C Al O/C A Y Q Q (F-8) *tHR Heat Enchanger
, (HX) Train A to CVCS Charge Pump SucLion HV 88048 2 212 IX4D8122 8 8.00 CA fl0 C AI O/C A Y Q (8-8) Q RHR HX Train 8 to Safety in-J ec & i c's Pump Suction HV 8811A 2 212 IX4DB122 8 14.00 CA MO C AI O/C A Y Q (15-3 ) Q Containment Sump. asoea-tion HV 83118 2 212 IX408122 8 14.00 CA MO C Al O/C A Y Q (8-3) Q Containment Saamp Isole-
! tsun ItV 8812A 2 212 IX408122 8 12.00 CA MO O AI O/C A Y Q Q (F-4) RHR Pump F6-OO3 Intet Irom RWST Hy 88128 2 212 IX408122 8 12.00 CA MO O At O/C A Y Q Q (C-4) RHR Pump r6-DO2 an-let I nue RWST PSV STO8A 2 212 IX4D8122 C 3.00 SR (H-3)
S C M/A O/C A T RHR Pump P6-OOi Intet PSV 87088 2 212 IX4C8122 C 3.00 SR S (E-3)
C N/A O/C A T RHR Pump P6-OO2 Inlet 00311 4-22
1 i
V[CP Unit 100 1 Valve Test List 008 REV 3 Syatem: ResidueI Hemt Remove 1 - System flo. 1205 Sheet 2 of 2 Valve Relief Valve Act. Reg. or Class P8ID Size Act. Poitition or Ilyshgr 111 Prvj. . (Coord. ) les h and Freg. C. S. Desc ript ion C_g iIn.1 Type Jype 8eo rm f a i l Safety Pass. ?_1 M si L$y M _.pyst._ end 800tes U4 122 2 212 1X408122 C 14.00 CK (C-3)
S C N/A O/C A Q RHft Sump Suctior.
(8eote 33 U4 123 2 212 1X4D8122 C 14.00 CK S C N/A O/C A Q (6-3) RHR Sump Suction (Note 3)
U6 001 2 212 IX408122 C 12.00 CK S C N/A O/C A PQCS CS-36 (F-4) Q RR-2 RWSi to l
RHR Pump suction U6 002 2 212 EM408122 C 12.00 CK S C SI/A O/C A PQCS CS-36 RWSi to (C-4) Q RR-2 l RHR Pump Siection U6 009 2 212 1X408322 C 8.00 CK S C N/A O A PQCS CS-37 RHR Pump (C-5) Rk-2 PC-001-Discharge Check U6 010 2 212 1X408122 C 8.00 CK S C N/A O A PQCS CS-37 RHR Pump (D-5)
HR-2 P6-002 Osscharge Check FV 0610 2 212 IM408322 6 3.00 CA MO O AI O/C A Y Q Q (H-5) RHR Panap P6-001 Minirsow IV 0611 2 212 1X408122 8 3.00 CA MO O AI 0/C A Y Q Q RHR Pump
([-5)
P6-002 Minsr ow 0031s 4-23
.. p VECP Unit No. 1 Valve Test List 008 REV 3 Syston: Containment Spray - System No. 1206 Sheet 2 or 2 Yalve Retier Valve Clay 1 P&ID Act. Req. or Site Act. Polition or W_f [S1 Rro_E _1_Qgord.). Gag N Jyg Jyg Tests and Free. . C. S. Description
,000_re f a il Sa fety Pass. PI U }I F}y Q Jnk and 100tes U6 015 2 212 IX408131 AC 8.00 CK S C A II/A O/C Ret R RR-2,14
( 89-7 ) CS anboard Containment Check VaIve (Note 1)
U6 016 2 212 1X4D8131 AC 8.00 CK (C-T)
S C N/A O/C A RH R RR-2,14 CS Inboa rd Containeent Check Vaave (Note 1)
U6 03T 2 212 1M408131 C 3.00 CK (F-3)
S C N/A O/C A Q Spray Addi-teve tank to Iraen A NaOH [duc-ter Check U6 038 2 212 1M4D8131 C 3.00 CX S M/A O/C C A Q (E-5) Spray Addi-i teve Tank
! to Train 8 NaOH Edoc-tor Check
- 3 313 1X408131 C 1.00 SR S C ft/A O A i vacense (F-4) g a
B reake rs
' Spray additive tank vscuum breakers (2) l 4
00318 sa-23 1
j .
6 RELIEF REQUEST RR-26 Relief Request Withdrawn 5-26 REV. 3
t .
t COLD SHUTDOWN JUSTIFICATION CS-35 Cold Shutdown Justification Withdrawn 1 6-35 REV, 3
~
4
, +
k COLD SHUTDOWN JUSTIFICATION CS-36 SYSTEM: Residual Heat Removal - System No. 1205 VALVE (S): 1205-UC-001, 1205-06-002 CATECORY: C CLASS: 2 FUNCTION- Thess check valves open to allow flow from the refueling water sterage tank to the residual heat removal pumps. These valves close to prevent reverse flow to the refueling water storage tank.
QUARTERLY TEST REQUIREMENT: Verify forward flow operability and reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: During normal operation, the RHR pumps cannot overcome RCS operating pressure.
Fcrward flow operability of these normally closed check valves during normal operation can be verified only by aligning the RHR system to circulate water to and from the RWST. However, this alignment provides only partial flow through the check valves. Reverse flow
- losure will be varified quarterly.
QUARTERLY PARTIAL STROKE TESTING: These valves will be partial stroke exercised quartarly.
COLD SHOIDOWN TESTING: These valves will be tested during cold shutdown. The maximum required flowrate through each valve wil.' be verified.
6-36 REV. 3
i . .a l
's COLD SHUTDOWN JUSTIFICATION C3-37 SYSTEM: Residual Heat Removal - System No. 1205 \
{
VALVE (S): 1205-U6-009, 1205-U6-010 CATEGORY: C t CLASS: 2 FUNCTION: These valves are the RHR pump discharge check valves which functions. are required to open to support various safety QUARTERLY TEST REQUIREMENT: Verify forward ilow operability.
COLD SHUTDOWN TEST JUSTIFICATION: During normal operation, the RHR oumps cannot overcome RCS operating pressure.
Forward flow operability of these normally closed check valves during normal operation can only be accomplished by pumping in the miniflow circuit or by pumping back to the RWST. However, both of these test circuits allow only partial flow through the check valves.
QUARTERLY PARTIAL i
STROKE TESTING: These valves will be partial stroke '
exercised quarterly.
l COLD SRUTDOWN TESTING: These valves will be tested during cold shutdown. The maximum required flowrate through each valve will be verified.
I 6-37 REV. 3
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