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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Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for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
i ATTACHMENT SOUTH TEXAS PROJECT UNIT 2 CYCLE 4 STARTUP TESTING
SUMMARY
REPORT
)
l l
9408250100 94081'7 PDR ADOCK 05000499 p
PDR MISC-94\\94 220.001
l South Texas Project Unit 2 Cycle 4 Attachment Low Power Physics Testing Page 1 of 4 1.
CRITICAL BORON CONCENTRATIONS (PPM):
Design Review Criteria (DRC):
ISO ppm il5% of Delta (19 ppm)
Acceptance Criteria (AC):
i1000 pcm (140 ppm)
Predicted Measured (M-P)
Pass / Fail Pass / Fail (P)
(M) ppm DRC AC ARO 1805 1766.1
-38.9 P
P CBC-in 1675 1646.4
-28.6 P
130 119.7
-10.3 P
(ARO - BC-in) 11.
ROD WORTil MEASUREMENTS (Rod Swap Method Used):
Design Review Criteria (DRC):
Reference Bank (CBC) within 10% of predicted Other banks within 15% or 100 pcm (whichever is greater)
Total s 110% of predicted Acceptance Criteria (AC):
Reference Bank (CBC) within 15% of predicted Other banks within 30% or 200 pcm (whichever is greater)
Total 2 90% of Predicted Predicted Measured Delta Percent Pass / Fail Pass / Fail RCCA Bank Worth Worth (M-P)
Difference DRC AC l
(pcm)
(pcm)
(pcm)
(%)
i Control A 757 709.1
-47.9
-6.3 P
P Control B 758 733.9 25.9 3.4 P
P Control C 871 855.3
-15.7
-1.8 P
P Control D 498 477.2
-20.8
-4.2 P
P Shutdown A 324 342.9 18.9 5.8 P
P Shutdown B 714 679.1
-34.9
-4.9 P
P Shutdown C 418 425.5 7.5 1.8 P
P Shutdown D 419 422.9 3.9 0.9 P
P Shutdown E 336 299.0
-37.0
-11.0 P
P Total 5095 4994.9
-100.1
-2.0 P
P ARO: All Rods Out CBC: Control Bank C Percent Difference = 100 x (M - P) / P MISE.94\\94-220.001
South Texas Project Unit 2 Cycle 4 Attachment Low Power Physics Testing Page 2 of 4 III.
DIFFERENTIAL BORON WORTII(PCM/ PPM):
Design Review Criteria (DRC):
il5%
Acceptance Criteria (AC):
none Percent Pass / Fail Pass / Fail Predicted Measured Difference DRC AC
-7.15
-7.15 0.0%
P IV.
ARO ISOTilERMAL TEMPERATURE COEFFICIENT (ITC)(PCM/ F):
Design Review Criteria (DRC):
3 pcm/ F Acceptance Criteria (AC):
none PassNail Pass / Fail Predicted Measured Error (M-P)
-3.3
-3.34
-0.04 P
V.
INFERRED ARO MODERATOR TEMPERATURE COEFFICIENT (PCM/ F)*-
Design Review Criteria (DRC):
none Acceptance Criteria (AC):
< 0 pcm/ F, or rod withdrawal limits established Pass /I all Pass / Fail Predicted Measured Adjusted
-1.4
-1.44
-0.64 *
- P Inferred MTC is obtained by subtracting the Doppler Temperature Coefficient (-1.9 pcm/ F) from the Isothermal Temperature Coefficient.
Adjusted MTC includes measurement uncertainty and IFBA correction.
MISC-94L94 220 001
r-l South Texas Project Unit 2 Cycle 4 Attachment Power Ascension Testing Page 3 of 4 l
VI.
POWER DISTRIBUTION MFASUREMENTS:
Design Review Criteria (DRC):
Incore Tilt (based on F-Delta-H) s 1.02 Reaction Rate Errors < 10 %
Acceptance Criteria (AC):
FDlIN < Technical Specification (TS) 3.2.3 Limit F s TS 3.2.2 Limit xy Largest Unrodded Reactor incore Quadrant Highest FDHN Limiting Limit Rea,on Power Power Tilts FDHN Limit F
xy xy Error (%)
1.ow Power 1.0037 0.9990 1.5023 1.7700 1.7051 1.9315 12.0*
(29.2%)
1.0024 0.9949 Intermediate 1.0050 0.9986 Power 1.4792 1.693 1.6755 1.8724 11.4*
(46.7%)
1.0029
.9935 Intermediate 1.0076 0.9938 Power 1.4371 1.557 1.6280 1.7673 6.5 (77.7%)
1.0002 0.9985 1:ull Power l.0050 0.9976 1.4051 1.4600 1.5881 1.6921 6.7 (l00.0%)
1.0025 0.9950 FDilN: Nuclear Enthalpy Rise Hot Channel Factor Core periphery location wsemnno ms
South Texas Project Unit 2 Cycle 4 Attachment Power Ascension Testing Page 4 of 4 Vll.
REACTOR COOLANT SYSTEM FLOW MEASUREMENT (GPM):
Design Review Criteria (DRC):
none Acceptance Criteria (AC):
> 395,000 gpm Pass / Fail Pass / Fail Reactor Power Measured Flow DRC AC 70.8 %
406,658 P
99.3 %
404,955 P
Vill. FULL POWER CRITICAL BORON (PPM);
Design Review Criteria (DRC):
50 ppm Acceptance Criteria (AC):
11000 pcm (145 ppm)
Burnup Pass / Fail Pass / Fail Predicted Measured (M-P)
DRC AC (EFPD) 17.I 1210.5 1168.8
-41.7 ppm P
P MISCA434-220 Otn i