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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999
Rev 4 to Severe Weather Plan, Including Summary of Changes.With
ML20217A2421999-09-30030 September 1999
Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow
ML20211Q8071999-09-0808 September 1999
Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements
ML20211Q2361999-09-0808 September 1999
Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR
ML20211G2281999-08-24024 August 1999
Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List
ML20211C0371999-08-18018 August 1999
Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs
ML20210J0481999-07-28028 July 1999
STP Unit 1,Cycle 9 Startup Testing Summary Rept
ML20209G9351999-07-15015 July 1999
Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves
ML20209H3371999-07-13013 July 1999
Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting
ML20209H2131999-07-13013 July 1999
Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification
ML20209G4461999-07-13013 July 1999
Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations
ML20209C1511999-07-0101 July 1999
Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan
ML20209B5341999-06-24024 June 1999
Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR
ML20209H3151999-06-23023 June 1999
Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management
ML20195E4701999-06-0707 June 1999
Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2
ML20195E4211999-06-0707 June 1999
Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR
ML20209H3081999-06-0101 June 1999
Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program
ML20205S3511999-04-19019 April 1999
Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3
ML20205G8081999-03-30030 March 1999
Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431
ML20204J9681999-03-22022 March 1999
Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves
ML20204D1581999-03-15015 March 1999
Proposed Tech Specs 3/4.7.9 for Snubbers to TRM
ML20207L9441999-03-0909 March 1999
Proposed Tech Specs,Removing Ref to Independent Safety Engineering Group from Requirements
ML20207D9651999-03-0202 March 1999
Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B
ML20207C4721999-02-24024 February 1999
Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance
ML20202G6871999-01-26026 January 1999
Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels
ML20199K5681999-01-20020 January 1999
Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing
ML20198A2181998-12-10010 December 1998
Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria
ML20198A1951998-12-0909 December 1998
Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon
ML20196B8121998-11-23023 November 1998
Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section
ML20155J9031998-11-0303 November 1998
Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools
ML20155D5801998-10-29029 October 1998
Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM
ML20155D5561998-10-29029 October 1998
Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM
ML20155D5441998-10-29029 October 1998
Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM
ML20154M1621998-10-12012 October 1998
Revised Tech Specs Bases Pages B3/4 8-14 Through -17
ML20154C0051998-09-30030 September 1998
Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria
ML20154C5071998-09-30030 September 1998
Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics
ML20154A4281998-09-28028 September 1998
Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys
ML20151T1621998-08-31031 August 1998
Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs
ML20238F0841998-08-28028 August 1998
Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code
ML20236T5141998-07-22022 July 1998
Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences
ML20236R1461998-07-15015 July 1998
Proposed Changes to Current Tech Specs Bases
ML20236L6311998-07-0707 July 1998
Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs
ML20236M6381998-07-0606 July 1998
Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual
ML20236N0001998-07-0606 July 1998
Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR
ML20236K3481998-07-0606 July 1998
Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual
ML20247F3321998-05-0707 May 1998
Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences
ML20217P1441998-04-0202 April 1998
Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria
ML20202H9771998-02-16016 February 1998
Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections
ML20198C3741997-12-31031 December 1997
Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow
ML20197A7211997-12-17017 December 1997
Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years
1999-09-08
[Table view]
Category:TEST REPORT
MONTHYEARML20210J0481999-07-28028 July 1999
STP Unit 1,Cycle 9 Startup Testing Summary Rept
ML20072G8031994-08-17017 August 1994
STP Unit 2 Cycle 4 Startup Testing Summary Rept
ML20092G4491991-11-19019 November 1991
Reactor Containment Bldg Integrated Leakage Rate Test Rept
ML20081G1271991-03-0404 March 1991
Reactor Containment Bldg Integrated Leakage Rate Test Rept
ST-HL-AE-3229, Startup Rept1989-09-18018 September 1989
Startup Rept
ML20196C0991988-11-15015 November 1988
Rev 1 to IE Bulletin 88-005 Investigation Rept,South Texas Project Electric Generating Station - Unit 2
ST-HL-AE-2734, Summary of Unit 1 Voltage Verification Test Results (PSB-1) South Texas Project Electric Generating Station1988-08-0202 August 1988
Summary of Unit 1 Voltage Verification Test Results (PSB-1) South Texas Project Electric Generating Station
ML20209D4231987-04-21021 April 1987
Actuation Train Relay Response Time Test Summary & Results
ML20215L0791987-04-17017 April 1987
Rev 1 to Purge Containment Isolation Valve, Operability Analysis & Test Rept
ML20215L0991987-04-13013 April 1987
Qualification Test Rept on Valve & Actuator for Valtek,Inc, Springsville,Ut
ST-HL-AE-2198, Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept1987-03-31031 March 1987
Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept
ML20206K6431987-03-20020 March 1987
Rept of Test Conducted to Determine Effects of Spraying Water on Anaconda Flex Conduit Wrapped in Siltemp WT-65. No Visible Damage or Siltemp Slippage Observed
ML20212M4771987-02-19019 February 1987
Energy,Inc Test Rept on Eight-Channel Digital Isolator
ML20215A4511986-11-30030 November 1986
Nonproprietary Noise,Fault,Surge & Radio Frequency Interference Test Rept
ST-HL-AE-1917, Electrical Test Rept on Isolation Relays & Transmitter & Receiver for Bechtel. Related Documentation Encl1986-09-16016 September 1986
Electrical Test Rept on Isolation Relays & Transmitter & Receiver for Bechtel. Related Documentation Encl
ML20206M3581986-01-0303 January 1986
Rev 2 to Door Sealing Matls Qualification File for Watertight Doors Mfg by Mosler Safe Co for South Texas Project Electric Generating Station
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
ML20064N8551984-10-12012 October 1984
Damper Test Rept for South Texas Project Units 1 & 2
ML20206M5281984-10-0101 October 1984
Damper Test Rept for South Texas Project Units 1 & 2
ML20138N8211981-07-0707 July 1981
Radiation Tolerance & DBA Results on Nupec Concrete Coating Sys
ML20138N7161981-06-10010 June 1981
Nutec 11S/Nutec 1201 Nutec 11S/Nutec 11/Nutec 1201 Radiation Tolerance,Dba Testing (Ornl)
ML20138N8761978-01-25025 January 1978
Compatibility Testing - Concresive 1411 Epoxy Mortar
ML20138P1141976-11-11011 November 1976
Nutec 10/11S/11/1201 Over Magic Kote Formed Concrete
ML20138N7121976-07-31031 July 1976
Recoatability of 560/1201 W/Nutec 1201 After 1 Yr Simulated Outside Exposure
ML20210C6771975-10-31031 October 1975
Rev 2 to Westinghouse Protection Sys Noise Tests
1999-07-28
[Table view] |
Text
South Texas Project Unit 1 Cycle 9 NOC-AE-000599 Startup Testing Attachment Page 1 of 5 ATTACHMENT SOUTH TEXAS PROJECT UNIT 1 CYCLE 9 STARTUP TESTING
SUMMARY
REPORT fjeogodk ((oo O
P
(
South Texas Project Unit 1 Cycle 9 NOC-AE-000599 Startup Testing Attachment Page 2 of 5 I
l l.
Ilot Rod Drop Time (secondsi:
Acceptance Criteria (AC):
2.8 seconds Measumd Pass / Fail (M)
AC 1.8
Rod Worth Measurements (Dynamic Rod Worth Measurement Method Used)(pcm):
Design Review Criteria (DRC): Each bank within 15% or 100 pcm of the predicted value (whicheveris greater)
Total rod wonh within 8% of predicted Acceptance Criteria (AC):
Total rod wonh 2 90% of Predicted RCCA Bank Measured Predicted Delta Percent Pass / Fail Pass / Fail Worth Wonh (M-P)
Difference DRC AC (Pem)
(pcm)
(pcm)
(%)
Shutdown A 554.7 541.8 12.9 2.4 P
Shutdown B 704.2 695.8 8.4 1.2 P
Shutdown C 538.4 531.0 7.4 1.4 P
Shutdown D 552.4 542.4 10.0 1.8 P
Shutdown E 474.0 479.0
-5.0
-1.1 P
Control A 765.6 739.9 25.7 3.5 P
Control B 847.1 815.2 31.9 3.9 P
Control C 880.9 838.5 42.4 5.1 P
Control D 502.3 473.0 29.3 6.2 P
Total 5819.6 5656.6 163.0 2.9 P
P ARO: All Rods Out
% Difference = 100 x (M - P) / P l
L
South Texas Project Unit 1 Cycle 9 NOC-AE-000599 Startup Testing Attachment Page 3 of 5 Ili.
Zero Power Critical Boron Concentration (ppm):
Design Review Criteria (DRC):
50 ppm Acceptance Criteria (AC):
11000 pcm (125 ppm)
Measured Predicted (M-P)
Pass / Fail Pass / Fail (M)
(P) ppm DRC AC 1457 1462
-5 P
P l
IV.
ARO Isothermal Temperature Coemcient (ITC)(ocm/ F):
)
Design Review Criteria (DRC): 12 pcm/ F Acceptance Criteria (AC):
none Measured Predicted Error (M-P)
Pass / Fail Pass / Fail (M)
(P)
DRC AC
-6.7
-7.2 0.5 P
V.
Inferred ARO Moderator Temperature Coemclent (pcm/ F)*:
Design Review Criteria (DRC):
none Acceptance Criteria (AC):
< +5 pcm/ F, or rod withdrawal limits established Measured Pmdicted Adjusted Pass / Fail Pass / Fail DRC AC
-4.9
-5.4
-3.9*
- P Inferred MTC is obtained by subtracting the design Doppler Temperature Coefficient
(-1.8 pcm/ F) from the measured Isothermal Temperatun: Coefficient.
Adjusted MTC includes measurement uncertainty and Integral Fuel Burnable Absorber burnout correction.
g -
t 9
South Texas Project Unit 1 Cycle 9 NOC-AE-000599 Startup Testing Attachment Page 4 of 5 VI.
POWER DISTRIBUTION MEASUREMENTS:
Design Review Criteria (DRC):
Incore Tilt (based on F-Delta-H) $ 1.02 Unrodded Reaction Rate Errors < 10 %
Acceptance Criteria (AC):
FDHN < Technical Specification (TS) 3.2.3 Limit Fxy5 TS 3.2.2 Limit Largest Reactor Power Incore Quadrant Highest FDHN Limiting Fxy Limit Re ion PowerTilts FDHN Limit pxy Rate Error (%)
Low Power 1.0083 0.9865 1.5641 1.894 1.8033 2.1149 10.9*
(27.8%)
1.0108 0.9944 Intermediate Power 1.0113 0.9992 1.4715 1.666 1.6921 1.9339
-7.8 (76.8%)
0.9957 0.9940 Full Power 1.0131
' l.0027 1.4410 1.557 1.6419 1.8480
-7.8 (100.0%)
0.9917 0.9926 i
I FDHN: Nuclear Enthalpy Ris-Hot Channel Factor Incore Tilt: Measur:d Incore Tilt in Excess of Designed Core Asymmetry
)
- Iacated in quadrant with highest power tilt and near core periphery - no corrective actions required.
=
I South Texas Project Unit 1 Cycle 9 NOC-AE4)00599 Startup Testing Attachment Page 5 of 5 VII.
Reactor Coolant System Flow Measurement (epm):
Design Review Criteria (DRC): none i
Acceptance Criteria (AC):
2 392,300 gpm Reactor Power Measured Flow Pass / Fail Pass / Fail DRC AC 99.9 %
397,692 P
VIII. Full Power Critical Boron (nom):
Design Review Criteria (DRC):
50 ppm Acceptance Criteria (AC):
11000 pcm (128.7 ppm)
Burnup Measured Predicted (M-P)
Pass / Fail Pass / Fail (EFPD)
DRC AC 3.1 882.3 880.8 1.5 P
P
,
