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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] Category:TEST REPORT
MONTHYEARML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17306A5911991-12-31031 December 1991 Reactor Containment Bldg 1991 Integrated Leak Rate Test Final rept.W/920319 Ltr ML17305B1921990-11-13013 November 1990 Piping Verification Test Summary. W/901113 Ltr ML17305A8411990-02-28028 February 1990 1990 Reactor Containment Bldg Integrated Leak Rate Test Final Rept. ML17304A6291988-10-31031 October 1988 Startup Rept,Suppl 1. ML17304A2551988-07-31031 July 1988 Suppl 1 to Palo Verde Nuclear Generating Station Unit 3 Startup Rept. ML20246H9871988-04-30030 April 1988 Environ Qualification of Continental Wire & Cable Corp Instrumentation Cable Installed in Beaver Valley Power Station Unit 1 ML20150E6711988-02-29029 February 1988 Vols I-III of Reciprocating Charging Pump Test Rept ML20155A9331987-12-24024 December 1987 Analysis of Reactor Coolant Pump Shaft W/Modified Key Region ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML17303A4551987-07-0101 July 1987 Piping Verification Program,Test Summary. W/870701 Ltr ML17300A9181987-06-30030 June 1987 Suppl 2 to Palo Verde Generating Station Unit 2 Startup Rept. ML20207R9931987-03-31031 March 1987 Suppl 1 to Palo Verde Nuclear Generating Station Unit 2 Startup Rept ML20207N0531986-12-31031 December 1986 Rev 0 to Palo Verde Nuclear Generating Station,Unit 2 Startup Rept ML17303A1811986-12-0101 December 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. W/861208 Ltr ML20215E4621986-11-30030 November 1986 Voltage Study for Split Group Bus Configuration ML20214T8891986-11-30030 November 1986 Suppl 3 to Startup Rept ML20214L8401986-08-31031 August 1986 Suppl 2 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML17300A2821986-07-15015 July 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML20210U6791986-05-31031 May 1986 Rev 1 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML20154D4671986-02-28028 February 1986 Startup Rept ML17299B0511986-02-24024 February 1986 Startup Experience Rept:Mgt Overview. ML20195C7791986-02-20020 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C7601986-02-20020 February 1986 Rev 1 to Seismic Instruments Channel Check ML20210T5271986-02-19019 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R140 (HPCS Pump Base Mat) ML20195C8941986-02-18018 February 1986 Rev 2 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R170 (Reactor Recirculation Piping Support) ML20195C8521986-02-18018 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R130 (HPCS Piping in Reactor Bldg) ML20195C7681986-02-18018 February 1986 Rev 1 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C8731986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R190 (RCIC Pump Base Mat). Related Documentation Encl ML20195C8671986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R180 (HPCS Pump Base Mat) ML20195C8601986-02-14014 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R160 (Reactor Bldg Foundation) ML20195C7391986-02-0707 February 1986 Rev 1 to Triaxial Time-History Accelerograph Channel Calibr ML20195C7521986-02-0707 February 1986 Rev 1 to Triaxial Seismic Switch Channel Calibr for D51-N150 ML20127J4031986-01-20020 January 1986 Safety Equipment Status Sys (Sess) Commissioning Test ML17299A9021985-12-24024 December 1985 Auxiliary Feedwater Pump 48 H Endurance Test Results, Per Sser (NUREG-0857).W/851224 Ltr ML20213G1521985-09-26026 September 1985 Sanitized Version of Test Program on Isolation Relays & Analog Signal Isolators for Use in Hope Creek Generating Station. W/Three Oversize Drawings ML20133N0211985-08-27027 August 1985 Electrical Cable Separation Verification Testing ML17299A3471985-05-0707 May 1985 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML20099E6561985-02-18018 February 1985 Rev 1 to Reactor Vessel Cavity Seal Test Results,Catawba Nuclear Station,Units 1 & 2,McGuire Nuclear Station,Units 1 & 2 ML20112J7191985-02-0404 February 1985 Rev a to Qualification Rept for Model KDI-1000 High-Range Containment Area Radiation Detector & Mineral-Insulated Cable Sys ML20104A9601985-01-18018 January 1985 Reactor Vessel Cavity Seal Test Results ML20198E7441985-01-10010 January 1985 Test Rept for Full Flow Testing of 16,18 & 20-Inch Main Steam Safety Valve Vent Stacks for Yankee Atomic Electric Co ML20137Z8271984-11-30030 November 1984 Nuclear Component Qualification Test Rept Square D 9025-BCW-45 Thermal Switch ML17298B5721984-10-24024 October 1984 Preliminary Prompt Notification Siren Sys Test Rept for 841024 Test. ML20098F5441984-09-30030 September 1984 Rev 0 to Evaluation of Tests Performed on Energy Absorbing Matl for Pipe Whip Restraints ML20100N1091984-08-31031 August 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 8, Final Rept ML20094C1511984-07-12012 July 1984 Extension of Retainer Lifetime to 4 Cycles ML20094G7451984-04-30030 April 1984 Rev 1 to Evaluation of Energy Absorbing Matl for Pipe Whip Restraints ML20138P4551984-04-19019 April 1984 Elcometer Adhesion Tests Nutec Concrete Coating Repair Sys 11S/1201/11S/1201 11S/1201/11/1201. Related Documentation Encl ML20100N1151984-03-31031 March 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 18, Final Rept 1994-02-24
[Table view] |
Text
,4 TEST RESULTS REPORT
[
{- PROCEDURE NO._ 91HF-1RC01 PROCE6URE IITLE RCS Expansion Measurements REVISION AT THE ColiMENCEMENT OF TESTING _ 0 DATO 4-6-83 REVISION AT COMPLETION OF TESTIN'G 0
+
DATE 4-6-83 LATEST TEST CILO'CE NOTICE NO. 08 DATE 6-25-83 DATES OF TEST PERFOR)%NCE 4-11 7-15-83 PAGE 1 OF 3 f
Review and Approval of Test Results '
PREPARED BY: jy e -
DATE: 7 83 TECHNICAL REVIEW gh DATE: ~/- 26~- 83 GROUP SUPERVISO REVIEV:
%,- 2, DATE: 7-17-8,3 v-TEST WORKI:C CROUP MEETING NO!EER: DATE:
PLANT REVIEW BOARD MEETII:G NC1BER: DATE:
QUALITY ASSURANCE REVIEW: DATE:
(Required for Test Respits Reports not reviewed by TUG)
STARTUP 1% NAGER APPROVAL: DATE: '
8402080123 831116 e PDR FDIA 54-b7Y GARDE 83-609 PDR w - , , , - - - - ,e-- n m , - - -- w- r-o- --g, -s ,---
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91hi-Ikt01 O
A. TEST PURPOSE AND SCOPE:
~
Esv. O TCN 8
- Pag 2 2 cf 3 ThaRCS the purpora of thisand to expand testcontract w s to demonstrate the unobstructed freedom of
( verify correct sizing of various RCS support shims.during plant heatup and cooldo included in this test were all cajor RCS components including RCS piping .
B. COMPLEMENTARY TESTS:
90HF-12201 Precore Hot Functional test C. TEST DESCRIPTION: -
At the by: various test plateaus RCS components were observed for even expansion a.) visual observation b.) go no-go measurements c.) measurements at predetermined locations These measurements were compared to the original cold ambient measure-ments and also against each other to assure that no component was locked up.
- Feeler gages, vernier calipers, used.to obtain the measuremente. tape measures and similar hand tools were Cr;.pacitance probes were used on an lower lateral supports. experimental basis to measure the gaps at the Reactor Ve measure temperature at Additionally, thermo couples were installed to the top and bottom of the Reactor support column.
C. TEST EVENTS:
(
Prerequisite sign offs were started April 11, 1983 and were completed on 05-09-83. .
Initial ambient measurements were started on 05-09-83 and final ambient measurements were completed 07-13-83.
Throughout the heatup and cooldown to major problems were observed. There was minor interference with insulation being deformed at the Steam Generator key areas and at the top of the Pressurizer, and some of the small piping coming off the RCPs was' restricted from moving. Additional problems were bolts on pressurizer key shims. interference of RCP 2A motor cooler with a the above problems: The following SFRs were written to document SFR #
DESCRIPTIO_N 1RC-092 IRC-105 RCP 2A motor cooler IRC-106 RCP 1B bleed of piping IRC-110 RCP 2A pump casing drain IRC-111 pressurizer mirror insulation IRC-115 miss'ing bolts on pressurizer shim plate 1RC-120 pressurizer #2 keyway 1RC-122 RCP 2B bleed off piping RCP 2B casing vent IRC-121 ISG-137 RCP 2A bleed off piping ISG-138 S/G #1 mirror insulation S/G #2 mirror insulation All required measuremen's were obtained to facilitate sizing final shims .
for thesupports.
, lateral steam generato. sliding base cross stops and for the lower RV
. any new 91HF-1RC01
-[ Rev. O TCN 8 t
,( D. TEST EVENTS (cont'd): ,
.Due'to the unscheduled cooldowns and subsequent heatups it was found acceptable to delete the 460 and 260 F cooldown plateaus. TCN 08 reflects this change in the procedure. During the above mentioned cooldowns and heatups the RCS was closely monitored visualIy and by actual' measurements.
'Ihese measurements are documented as part of. the test Icg. The procedure performed-very well in achieving its. goals and mostly only minor changes were required.; A total of 8 TCNs were required and are listed below.
TCN # Scope /Non Scope Description 01 scope change snubber acceptance criteria 02 scope add additional appendices 03 non scope delete note with regard to 24 hr. time period prior to start of test 04 non scope interchange of available control room instrumentation 05 non scope add additional measuring tools 06 scope add Reactor Coolant Pumps "V" dimensions to correct saveral tgpos 07 non scope 08 scope delete 460 F and 260 F cooldown plateaus.
E. TEST RESULTS:
Obtained measurements fell well within the required acceptance criteria with the exception of dimension 'LL' of the #2 pressurizer key at the 565 F plateaus which has been documented by TERs 01 and 02 and SFR-1RC-115.* The system responded well and repeatability thru the various heatup / cooldown cycles was excellent. One of the installed capacitance probes failed at the
- final ambient plateau (TER03). This was only for supplemental data and had no
'effect on the test results.
l; I
F. CONCLUSION:
'As installed the RCS expanded as was expected with no binding or sticking of the major components. Movements were as expected and after cooldown all components returned.to their starting position within a 1/16". The system as installed will perform as designed. 1 C. REComCNDATIONS:
Based on the results of the test, no retesting of the system is required with the exception of areas where additional shims will be installed and which will be tested in accordance with Post-Core Hot Functional procedure 73HF-1RC07. The procedure as written and the methods employed to obtain the measurements were more than adequate and no changes are recommended. Based on the above approval of the test results is recommended.
- Retest will be conducted during Post-Core Hot Functional Testing.
L