|
---|
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
- - -. .
i ,
. TEST RESULTS REPORT PROCEDURE NO. 93HF-1MA05 PROCEDURE TITLE Main and Auxiliary Transformer Backfeed REVISION AT THE COMMENCEMENT OF TESTING Rev. O DATE 10-8-82 REVISION AT COMPLETION OF TESTING Rev. O DATE lb-8-82 LATEST TEST CHANGE NOTICE NO.. 004 DATE 7-22-83 DATES OF TEST PERFORMANCE 4-20-83 thru 5-15-83 PAGE 1 0F 5 C .
Review and
_ Approval of Test Results
~
PREPARED BY: > DATE: I~
l TECHNICAL REV : *4 DATE: 7- 2 /- 8 M
GROUP SUPERVISOR REVIEW: , / DATE:
%'2 /] N TEST hURKING GROUP MEETING ER: DATE:
PLANT REVIEW BOARD MEETING NUMBER: DATE:
i
! QUALITY ASSURANCE REVIEW: DATE:
(Required for Test Results Reports not reviewed by TWG)
STARTUP MANAGER APPROVAL: DATE:
- C ..
fp - 5 2 5 -- hh2 19 831116 CARDE83-609 PDR
. f
.~ . - - .~ .
a- ei Test Results Report 93HF-1MA05 Rev. O TCN 2 of 5 Page TEST PURPOSE ,
To verify through 'energization the . integrity of the Unit #1 Main Transformer E-MAN-X01A -X01B -X01C and the Unit Auxiliary Transformer E-MAN-XO2.
To provide baseline data for the Unit Auxiliary Transformer when-subjected to load.
To verify proper operation of the generator 525KV breakers to include breaker OPEN/CLOSE and trip circuits.
To provide baseline data for phase angle relationship of isophase bus to 500KV yard bus.-
verification of. proper operation of motor operated disconnect 525-910
- and proper phase rotation of bus E-NAN-S01 and S02. ~
SCOPE The scope of testing for this procedure involved the testing of the
! main generator breakers tripping OPEN/CLOSE circuits using either manual actuation of.the protective relay devices or simulation of
. permissive or trip signals using momentarily installed jumpers.
The motor operated disconnect switch was functioned in the
.(
-f
- - de-clutched position from its hand switch located on the main control board. Indicating lights were verified to correspond to the position Lof the switch.
I The main and unit auxiliary transformers were energized using the 525KV generator breaker 525-918. Readings were taken of voltage and phase angle at both the generator isophase bus and the 13.8KV breakers Temperature
-E-NAN-S01A'and E-NAN-S02A to verify proper outputs.
. readings were recorded at specified intervals on both the unit main i
transformers and unit auxiliary transformers.
< (
COMPLEMENTARY TESTS The following pre-operational tests were necessary to be completed prior to the energizing of the main transformer:
93PE-1MA03 Unit Auxiliary Transformer 93PE-1MA04 Main Transformer 93PE-lMA02 Isophase Bus It was necessary to have the following systems tested and in operation for the performance of 93HF-lFM05:
1FP-11 Unit Auxiliary XFMR Fire Protection 1FP-14 Main Transformer Fire Protection Testing of the 525KV breakers was the responsibility of the Salt River
( Project. They were contacted by letter and phone to verify proper
Test Results Report a
93HF-1M05 Rev. O TCN Page 3 of 5 operation of the 525KV breakers and they cooperated in the functional testing of the interface points between APS and SRP. No FSAR commitment has been made concerning this test.
TEST DESCRIPTION Testing in general was performed either by actuation of the normal control element or by simulation of a control element or trip function by the use of momentary jumpers.
Testing of motor operated disconnect switch #910 was conducted using the normal control switch located in the main control room. No protective relay devices are associated with this motor operated disconnect switch.
- Generator breakers 915 and 918 were functioned using the normal control -
switches located at the main control panel. The protective relay circuits associated with the main generator breakers were either actuated by manually turning the protective relay disk or by the use of jumpers being momentarily plac.ed across connection points on the relay. The breakers were tripped by manually actuating lockout relay 586T2. Each breaker was actually tripped by the manual actuation of the 586T2 relay both from a primary and backup trip scheme. The proper association of C test switch with lockout relay was verified by opening the test switch and attempting a trip of its associated lockout relay,, verifying that the lockout relay did not trip with the test switch OPEN and then closing the test switch and verifying that the lockout relay tripped.
Simulations of auxiliary contacts contained in breakers 525-915 and 525-918 were performed with jumpers at the specific breakers to provide actuation of relays 552X-1 (552X-2). -
Manual actuation of relay 552X-3 verified a circuit exists between relay 552X-3 and the generator distance backup relay and also that a permissive signal has been transmitted to the TSI cabinet.
Energization of the Unit #1 main transformer via breaker 525-918 furnished a baseline data source which provided unload temperature data on each main transformer and a phase angle relationship between the primary of the main transformer and the 500KV yard bus. Also, the voltage output of the main transformer was recorded on the isophase bus at the main generator potential cabinets.
Energization of the Unit #1 main transformer and the unit auxiliary transformer E-MAN-X02 provided a record of baseline data temperatures for both the main transformer, with a secondary load, and the unit auxiliary transformer unloaded. Euergization of the unit auxiliary
- transformer provided a method to verify the phase angle relationship between the secondary of the unit auxiliary transformer and the 13.8KV buses E-MAN-S01 and E-NAN-S02.
L
6 Test Results Report 93HF-1MA05 Rev. O TCN Page 4 of 5 f
TEST EVENTS Testing on procedure 93HF-lMA05 started on April 20, 1983 and was
).
completed on May 15, 1983.
- The testing required to arrive at a point where the main and cuxiliary transformers could be energized required a time period of approximately seven (7) days.
On 4-27-83 we attempted to close motor operated discor.nect MOD 910 using the hand switch located in the main control room. This attempt was not successful. It was determined that n misalignment was present in the limit switches at MOD 910. A manual realignment was accomplished using the hand crank furnished with the MOD and the switch was then able to be closed from the main control room. -
__ m The Unit #1 main transformer E-MAN-X01A -X01B -X01C was energized via 525-918 on 4-27-83 at 1823 hrs. At approximately 1825 hrs. main generator breaker 525-918 tripped. Upon investigation, it was determined that the Salt River Project relay technicians involved with the 525KV
. yard relay testing had inadvertently removed a relay test plug from the 525KV bus differential relay which caused breaker 525-918 to trip. This problem was corrected and approval was received from system operations and
( control (SOC) to reclose breaker 525-918, whir.h was accomplished at 1856 hrs.
No further problems were encountered during the backfeed of the Unit #1 main transformer and the transformer was de-energized af ter a period of five hours.
On 5-11-83 at 1620 hrs. breaker 525-918 was closed and the unit main transformer E-MAN-X01A -X01B -X01C with the unit auxiliary transformer -
E-MAN-X02 were energized. No problems were encountered during the eight (8) hour log period. The backfeed configuration was maintained for five days due to operational requirements during hot functional testing. No problems were noted during the five (5) days that the backfeed configuration was energized.
The problems encountered with the motor operated disconnect 910 were reported to Salt River Project and will be corrected as soon as possible.
TEST RESULTS The test results obtained satisfy the values required by the acceptance criteria.
The only problem encountered during the testing was that enccuntered with the motor operated disconnect MOD 910. These problems have been documented to Salt River Project by letter dated May 23, 1983 and will be worked when conditions allow.
c
.e
'1*-
Test Results Report 93HF-1.'M05 Rev. O TCN
.{ ,
Page 5 of _5 CONCLUSIONS The test data derived from procedure 93HF-lMA05 proved that the system equipment involved in this test will function according to the station design criteria. The following conclusions were derived from tha test data obtained:
The control and breaker trip functions for the main generator breakers performed properly.
The main transformer and auxiliary transformers running temperatures did not exceed the factory suggested limits.
The voltage limits and phase angle relationships supplied by the unit main end auxiliary transformers was within acceptable limits.
Ths protective relay circuits and associated equipment for protection of the main generator, main transformers, and auxiliary transformers performed according to the logic on the implementing references.
RECOMMENDATIONS No additional testing was found to be required.
The following changes in test t, hniques are suggested to be incorporated to simplify data taking and to limit unnecessary and repetitive readings: '
,' The readings taken on the generator isophase bus and the 500KV switch yard could be limited to one reading when first energized and another just prior to de-energizing.
The temperature readings taken on both the main transformers and the unit auxiliary transformers could be taken at one
~ half hour intervals rather than the fifteen minute intervals stated in the existing procedure.
It is suggested that the test results be accepted and that the procedure be approved as submitted.
t