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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Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for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
[Table view] |
Text
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STP 724 (02/90)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
""8" "
ISEG-01
- INDEPENDENT SAFETY ENGINEERING GROUP 5 ORGANIZATION AND RESPONSIBILITIES DTECME DATE 07/08/93 Approval: $N Date: 2.F!T 7 Manager, Nuclear Licensing Approval: M Date: d~ AI' k
/ Director, ISEG f 5i % i
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STP 724 (02/90) {
SOUTH TEXA8 PROJECT ELECTRIC GENERATING STATION ""8" ISEG-01 E- ;
INDEPENDENT SAFETY ENGINEERING GROUP 5 j ORGANIZATION AND RESPONSIBILITIES E 07/08/93 l r
l 1.0 PURPOSE '.
This procedure describes the structure, functions, and general i responsibilities of the STPEGS Independent Safety Engineering Group (ISEG). ;
2.0 SCOPE
- m. This procedure applies to the STPEGS ISEG.
3.0 DEFINITIONS '
None. l i
4.0 REFERENCES
4.1 STPEGS Final Safety Analysis Report Section 13.4.2.2. !
l 4.2 STPEGS Technical Specifications Section 6.2.3. t 4.3 NUREG 0737, Clarification of TMI Action Plan :
Requirements (November 1980), Item I.B.1.2. j
4.4 OPL-4422
W. J. Jump memorandum, " Independent Safety i Engineering Group." ;
4.5 IP-1.49, Independent Safety Engineering Group (ISEG) !
Reports and Responses. l 5.0 RESPONSIBILITIES 5.1 The Director, ISEG is responsible for:
5.1.1 Ensuring that regulatory requirements and other commitments associated with ISEG are identified and implemented.
5.1.2 Ensuring that ISEG actively pursues the objectives described in this procedure . while complying with requirements and commitments.
5.1.3 Coordinating and supervising the activities of ISEG.
5.2 ISEG personnel are responsible for complying with
, applicable ISEG procedural requirements, performing assigned tasks and collateral duties, and achieving the intentions expressed in this procedure.
I i
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l STP 724 (02/90) l
- "*'S *- l SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Na ISEG-01 l INDEPENDENT SAFETY ENGINEERING GROUP 5 l ORGANIZATION AND RESPONSIBILITIES DTECTWE DATE 07/08/93 6.0 REOUIREMENTS 6.1 Organization and Staffing 6.1.1 Organization 6.1.1.1 A generic ISEG Organization Chart is shown in Exhibit ISEG-01-A.
6.1.1.2 The Director, ISEG reports directly to the Manager, Nuclear Licensing.
6.1.1.3 ISEG staff reports directly to the Director, ISEG.
6.1.2 Minimum Staff Complement 6.1.2.1 The ISEG technical staff includes at least five full-time individuals assigned to the STPEGS Plant Site. -
6.1.2.2 The Director, ISEG may be counted in the minimum staff complement, if qualified, for compliance with that requirement.
6.1.3 Staff Qualifications 6.1.3.1 Individuals counted for the minimum staff complement requirement have a bachelors degree in engineering (or related science),
and four or more years of professional level experience, at least two years of which is in the nuclear power industry. These individuals are familiar with nuclear plant operations, maintenance, or support activities. Additional personnel not having these specific qualifications may also be assigned to ISEG. ,
6.1.4 ISEG Staffing 6.1.4.1 Personnel assigned to the ISEG acquire skill in performing observations and reviews of operating and support activities as well as in-depth activity effectiveness assessments and investigations. Temporary assignments of external departmental personnel beyond the permanent ISEG staff is allowed to augment ISEG staffing and to develop the skills of the temporary personnel.
1 P
STP 724 (02/90)
SOUTH TEXA8 PROJECT ELECTRIC GENERATING STATION ISEG-01
,y INDEPENDENT SAFETY ENGINEERING GROUP 5 ,
ORGANIZATION AND RESPONSIBILITIES FRECTIVE DATE 07/08/93 6.1.4.3 The Human Resource Development Program may be used as a vehicle to select qualified ,
candidates for ISEG positions. ,
the Company Wide Posting
~
Additionally, System may be used to ensure interested qualified personnel are given consideration for available ISEG positions.
6.1.4.4 ISEG avoids reliance on contract personnel to satisfy the minimum staff requirement or '
for assistance other than for short term one time projects.
6.2 Function and Policy 6.2.1 Function 6.2.1.1 The function of ISEG is to independently l observe and review selected plant activitiss !
in order to provide senior management with additional insight as to where improvements can and should- be made to procedures, l equipment, and training to improve plant safety and reliability.
6.2.1.2 Functional objectives are achieved through !
the following actions:
l 6.2.1.2.1 Observation of operations, maintenance and support activities. Reviews of documentation associated with these activities, j 6.2.1.2.2 Administration of the Operating Experience Review (OER) Program per approved procedures.
6.2.1.2.3 Performance of in-depth assessments of how specific activities are (or have been) performed or of the physical condition of Plant systems / structures.
6.2.1.2.4 Investigation of selected plant incidents.
6.2.1.2.5 Assignments by the Nuclear Safety Review Board (NSRB) such as reviews of Licensee Event Reports, significant industry events, etc.
. STP 724 (02/90)
SOUTH TEXA8 PROJECT ELECTRIC GENERATING STATION
.ISEG-01
- INDEPENDENT SAFETY ENGINEERING GROUP 5 ORGANIZATION AND RESPONSIBILITIES '
Entcms DAtt 07/08/93 1
6.2.1.2.6 Assessments or investigations as 3 requested by others as resources permit. l 6.2.2 Policy g 6.2.2.1 In order to maintain an accurate understanding of how activities are being performed, a priority. is given to viewing l activities in progress and the day-to-day physical condition of the Plant.
Documentation review alone does not provide an adequate picture of how appropriate and complete the activity planning and~
preparation was, how accurately and I completely the activity was documented, or -
how appropriately and effectively problems i encountered were dealt with. I I
6.2.2.2 ,
ISEG is aware of the opportunity they have- I to provide senior management with an '
objective understanding of how well the STPEGS is operating. ISEG must maintain the.
highest professional standards and provide clear and concise information both to senior management and to the individual Plant departments.
6.2.2.3 ISEG communications (including reports) with other organizations utilize functional titles instead of identifying individuals by name when describing activities or events.
6.2.2.4 ISEG focus is on how activities are performed in general rather than in any one particular occurrence.
6.2.2.5 ISEG focus is on how ef f.e ctively the objectives of an activity are met rather than on procedural compliance or achievement of minimum required results/ performance alone.
6.2.2.6 ISEG maintains the independence and objectivity necessary to effectively focus on where improvements to Plant safety and- 1 reliability should be made. ISEG personnel shall have no production or audit signcff responsibility.
e
+ - + - e,- -r-=.e -- -e- e m - -a r -e.n- - - - - - - - - - r-- -
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'. l
, STP 724 (02/90)
~*
SOUTH TEXA8 PROJECT ELECTRIC GENERATING STATION ISEG-01 7- i INDEPENDENT SAFETY ENGINEERING GROUP <
PAGC 6y 8 l ORGANIZATION AND RESPONSIBILITIES j DAlt 07/08/93 '
i 6.2.2.7 Whenever conditions appear to present a '
potentially significant adverse Plant safety and reliability concern, ISEG personnel are l to immediately inform the responsible !
organization management", the Director, ISEG, f and the Task Lead (if applicable) . Such I conditions include those that may involve ;
entry into a Plant Technical Specification [
action statement, or may involve showing the l Plant to be in a condition outside the !
bounding assumptions of safety analyses, or f may present an immediate and significant :
industrial safety hazard, or which may l otherwise present an unjustifiable risk to Plant reliability. j i
6.2.2.8 When an observed situation warrants a l Station Problem Report (SPR) be written, the !
ISEG engineer is responsible to ensure it is ;
submitted. This can be accomplished by t either submittal by ISEG or by personal -
{
verification that others involved in the ,
activity have submitted the SPR. l 6.2.2.9 ISEG personnel are to warn individuals observed to be in immediate risk from a i significant industrial safety hazard. l 6.3 Relationship with Nuclear Safety Review Board (NSRB) l 6.3.1 ISEG maintains a close relationship with the r NSRB. This relationship is required by the i i
Technical Specifications and is accomplished via the following processes.
6.3.1.1 The Chairman is provided copies of ISEG [
final reports upon issuance. 5 i
6.3.1.2 ISEG provides a monthly report to the !
Chairman, NSRB on current initiatives and j activities.
6.3.1.3 ISEG procedures are reviewed, prior to !
issue, by the Chairman, NSRB. .
l 6.3.1.4 ISEG performs Tasks as requested by the NSRB subject to resource availability and Task priorities. ,
i i
i
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l
. STP 724 (02/90)
. SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION """ ."-
ISEG-01 INDEPENDENT SAFETY ENGINEERING GROUP
- ORGANIZATION AND RESPONSIBILITIES EFFECTIVE DATE 07/08/93 6.3.1.5 ISEG provides requested presentations to the NSRB. Presentations may be case studies, ISEG reports, results of reviews, etc.
6.3.1.6 NSRB provides a forum for review and resolution of ISEG issues when appropriate. ;
7.0 DOCUMENTATION None.
8.0 EXHIBITS 8.1 Exhibit ISEG-01-A - Independent Safety Engineering Group (ISEG) Organization Chart.
I I
l
. STP 724 (02/90)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION ISEG-01 E INDEPENDENT SAFETY ENGINEERING GROUP E PAGE 8y 8 ORGANIZATION AND RESPONSIBILITIES EFFECTIVE DATE 07/08/93 EZIIBIT Z8EG-01-A INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
ORGANIEATION CHART ISEG Director ISEG Secretary ISEG ISEG ISEG ISEG ISEG Engineer Engineer Engineer Engineer Engineer .
. t
. Other ISEG .
. Engineers and .
. Technical Specialists .
..........................