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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Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for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 ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting 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 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR 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 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 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 ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM 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 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 ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual 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 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 ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 1999-09-08
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
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 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 ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20212G0031997-10-21021 October 1997 Rev 2 to OPGP-04-ZA-0002, Condition Rept Engineering Evaluation Program ML20209H3321997-07-31031 July 1997 Rev 2 to 0PGP01-ZA-0304, Probabilistic Safety Assessment Risk Ranking ML20198E8411997-05-22022 May 1997 Rev 4 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations ML20217G8191997-02-15015 February 1997 Rev 16 to 0POP03-ZG-0009, Mid Loop Operation ML20198E8511996-10-28028 October 1996 Rev 5 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations ML20134J9951996-09-11011 September 1996 South Tx 1 Fuel Assembly Insp Program ML20148C9531996-07-15015 July 1996 Rev 0 to 0PGP04-ZA-0604, Probabilistic Safety Assessment Program ML20217F0001996-04-0101 April 1996 Rev 0 to Usqe 96-0101, Control Room Envelope HVAC Emergency Makeup Flow Control Damper B2HEFCV9585 Temporary Mod ML20097D4021996-02-0202 February 1996 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20097D3751996-02-0202 February 1996 Rev 0 to 0PGP02-ZA-003, Comprehensive Risk Mgt ML20097D3821996-01-0202 January 1996 Rev 0 to 0PGP02-ZA-XXXX, Probabilistic Safety Assessment Program ML20097D3881995-10-30030 October 1995 Rev 0 to 0AAA00-AA-0000, Configuration Control of Probabilistic Safety Assessment ML20149E0061995-10-20020 October 1995 Rev 1 to Procedure Usqe 92-0022, Proposed Change Evaluates Doses from Leakage of Sump Water Into Rwst ML20149E0561995-10-20020 October 1995 Rev 2 to OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 2 ML20093E7361995-10-0202 October 1995 Rev 0,Suppl 1 to ISI Plan for First Insp Interval of South Tx Project Electric Generating Station Unit 1 ML20149E0321995-06-0404 June 1995 Rev 2 to Procedure OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 1 ML20080G9091994-12-31031 December 1994 1999 Business Plan ML20217G8141994-11-22022 November 1994 Rev 2 to 0PGP03-ZA-0101, Shutdown Risk Assessment ML20078Q2561994-11-0707 November 1994 Rev 6 to OPMP04-JC-0002, Polar Crane Insp ML20078C5971994-10-26026 October 1994 Rev 4,Suppl 2 to STP Electric Generating Station Unit 2 Pump & Valve IST Plan ML20078C5961994-10-26026 October 1994 Rev 6,Suppl 2 to STP Electric Generating Station Unit 1 Pump & Valve IST Plan ML20078Q5651994-10-17017 October 1994 Rev 6 to OPGP03-ZX-0002, Condition Reporting Process ML20078Q7291994-10-17017 October 1994 Rev 10 to OPGP03-ZA-0090, Work Process Program ML20078Q8051994-10-17017 October 1994 Rev 2 to OPGP04-ZE-0310, Plant Mods ML20078Q5081994-08-29029 August 1994 Rev 7 to OPMP02-ZG-0011, Alternative Valve Packing & Live- Load Valve Packing ML20078Q5581994-06-24024 June 1994 Rev 5 to OPGP03-ZX-0002, Corrective Action Program ML20078Q7801994-06-0101 June 1994 Rev 2 to OPEP07-ZE-0007, MOV Tracking & Trending Program ML20078Q4021994-05-24024 May 1994 Rev 7 to OPOP01-ZA-0001, Plant Operations Dept Administrative Guidelines ML20064N4561994-03-21021 March 1994 South Tx Project Electric Generating Station Operational Readiness Plan Unit 2 ML20078Q5521994-03-0808 March 1994 Rev 2 to OPOP02-AF-0001, Auxiliary Feedwater ML20078Q2581994-02-14014 February 1994 Rev 5 to OPGP03-ZM-0021, Control of Configuration Changes ML20078Q5671994-01-25025 January 1994 Rev 8 to OPGP03-ZA-0090, Work Process Program ML20063K3251993-12-23023 December 1993 300 Ton Essential Chiller Bypass Mod Verification Test ML20058C4771993-10-25025 October 1993 Rev 0 to STP Restart Action Plan ML20083P6821993-10-19019 October 1993 Rev 1 to Dept Procedure 0POP05-EO-EC00, Loss of All AC Power ML20078Q7851993-10-15015 October 1993 Rev 0 to, Equipment History Program ML20058N7821993-10-14014 October 1993 STP 1994-98 Business Plan ML20083P6831993-09-15015 September 1993 Rev 2 to Dept Procedure 0POP04-AE-0001, Loss of Any 13.8 Kv or 4.16 Kv Bus ML20046A2161993-07-15015 July 1993 Field Change 93-1163 to Rev 0 to Procedure 0PGP05-ZV-0008, Siren Sys Activation,Testing & Documentation, Adding Caution to Conducting Manual Growl Test ML20062L1461993-07-0606 July 1993 Rev 3 to Speakout Program Instruction SPI-02, Classification of Concerns ML20045E9781993-06-29029 June 1993 Rev 4 to Pump & Valve IST Plan, for Stp,Unit 2 ML20045E9901993-06-29029 June 1993 Rev 6 to Pump & Valve IST Plan, for Stp,Unit 1 ML20078Q2751993-06-28028 June 1993 Rev 5 to ISEG-01, Independent Safety Engineering Group Organization & Responsibilities ML20062L2301993-03-0202 March 1993 Rev 2 to Speakout Program Instruction SPI-08, Speakout Review Committee ML20062L2101993-03-0202 March 1993 Rev 2 to Speakout Program Instruction SPI-07, Speakout Repts 1999-07-13
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, STP 724 (02/90)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION ""85 7 SPI-10 3 SPEAK 0UT PROGRAM INSTRUCTION SPI-10 l
PAGE 1 OF 4 POTENTIAL WRONGD01NG INVESTIGATIONS EFF C M %
1.O PURPOSE This instruction delineates how SPEAKOUT will handle investigations of potential wrongdoing and improper conduct, and reporting potential wrongdoing matters to the United States Nuclear Regulatory Commission (NRC) .
2.0 SCOPE This instruction applies to any issues, over which SPEAKOUT has cognizance, deemed a potential wrongdoing or improper conduct.
This instruction does not apply to issues related to the-Continued Behavior Observation Program or the Fitness For Duty !
Program.
3.O DEFINITIONS 3.1 Wrongdoing - The violation of an NRC requirement or a company procedure or policy designed to implement ^
NRC requirements or assure nuclear safety, under circumstances involving:
- a. Knowledge that the requirement, policy or procedure applied; and
- b. either deliberate intent to violate t',
requirement, policy or procedure or care 3 aos disregard for whether the requirement, N11cy or procedure was violated.
3.1.1 Careless disregard - When a person conducts an act, or intentionally fails to conduct an act which is required, knowing or having reason to know that the conduct ' is in violation of requirements, and that the conduct is more severe than mere negligence.
NOTE: Wrongdoing does not include simple cases of inadvertent error, nistake, or forgetfulness.
)
3.2 Improper Conduct - The violation of a procedure or ;
policy which is not designed to implement NRC !
requirements or assure nuclear safety. _
I 9312290265 900921 PDR ADOCK 0500049B P PDR
.- e STP 724 (02/90)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION "*8" E
SPI-10 3 SPEAKOUT PROGRAM INSTRUCTION SPI-10 PAGE2 OF 4 POTENTIAL WRONCDOING INVESTIGATIONS EFFECTIVE DATE 4/29/92 4.O REFERENCES 4.1 SPEAKOUT Program Instruction manual, SPI 08, SPEAKOUT Review Committee 4.2 SPEAKOUT Program Instruction manual, SPI 09, Recommendations / Suggestions 5.0 RESPONSIBILITIES 5.1 The Manager, SPEAKOUT Program, is responsible for the implementation and maintenance of this instruction. ,
5.2 The Manager, SPEAKOUT Program, is responsible for making the final decision concerning what matters contain a potential wrongdoing, who will perform the investigation, reviewing the investigation report and making recommendations to the SRC. 1 5.3. The Manager, SPEAKOUT Program, or designee, has the responsibility for reporting all potentially significant wrongdoing matters under investigation to the NRC Senior Resident Inspector, documenting same and coordinating such information with Licensing.
5.4 SPEAKOUT is responsible for maintaining the completed file of related correspondence and documentation of wrongdoing matters investigated by SPEAKOUT or other entities.
5.5 The SPEAKOUT Interviewer / Investigator is responsible for identifying any potential wrongdoing during the receipt or investigation of any concern and notifying the Manager, SPEAKOUT Program.
5.6 The SPEAKOUT Review Committee (SRC) is responsible for reviewing wrongdoing investigation reports and recommendations made by SPEAKOUT.
5.7 The SRC is responsible for determining whether l wrongdoing has occurred.
,'
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION wuam p SPEAK 0UT PROGRAM INSTRUCTION' SPI-10 SPI-10 3 0
POTENITAL WRONGDOING INVESTIGATIONS ERECVW DAE 4/29/92 6.0 REQUIREMENTS 6.1 WRONGDOING 6.1.1 When the SPEAKOUT Interviewer / Investigator receives a concern containing potential wrongdoing, the Manager, SPEAKOUT Program is notified.
6.1.2 The Manager, SPEAKOUT Program will review each SPEAKOUT Concern Record and Investigation Report for possible wrongdoing.
6.1.3 When the Manager, SPEAKOUT Program, determines that potential wrongdoing is evident, a decision will be made to 1) notify the NRC 2) immediately cause an investigation to be performed; 3) perform 2) above and allow SPEAKOUT to investigate the nuclear safety or nuclear quality issues; 4) gather additional information to support the potential wrongdoing prior to performing (1) or 2) above.
6.1.4 When a wrongdoing is revealed, SPEAKOUT will continue to retain responsibility for the investigation of the concern but may delegate responsibility to investigate the potential wrongdoing portion of the concern. This does not however, prohibit the SPEAKOUT Investigator from gathering information or facts that will aid the responsible entity in
.its investigation of the wrongdoing.
6.2 IMPROPER CONDUCT 6.2.1 Improper conduct will be investigated by SPEAKOUT at the discretion of Management.
6.2.2 Documentation of improper conduct investigations will be as dictated by the situation.
STP 724 (02/90)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
~
7 SPEAK 0UT PROGRAM INSTRUCTION SPI-10 PAGE 4 OF 4
POTENTIAL WRONGDOING INVESTIGATIONS DATE 4/29/92 6.2.3 SPEAKOUT will retain, as a minimum, a copy of documentation generated as a result of an improper conduct investigation conducted by SPEAKOUT.
7.O DOCUMENTATION 7.1 All documentation concerning any SPEAKOUT Investigation Report, including wrongdoing investigations, will be maintained in the respective SPEAKOUT Concern File Folder.
7.1.1 All Class 1 and wrongdoing concern documentation will be controlled, to include controlled storage of computer, microfilm, and hard file copy information.
7.1.2 The retention period for documentation concerning potential wrongdoing, if determined to be wrongdoing, is life of plant.
8.0 Attachments None i