Rev 3 to Engineering Assurance Dept Procedure EAD-4, Reporting of Design Process Review/Technical Assessment Results| ML20087N462 |
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| Site: |
South Texas  |
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| Issue date: |
06/15/1983 |
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| From: |
HOUSTON LIGHTING & POWER CO. |
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| To: |
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| Shared Package |
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| ML20087N434 |
List: |
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| References |
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| EAD-4, NUDOCS 8404030482 |
| Download: ML20087N462 (6) |
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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Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow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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I '. sousto= vowti:c a masa coWANY NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL
SUMMARY
OF REVISIONS
. .aoc no ] swasse, EAD-4 I Reportino of Desian Process Review / Technical Assessment Results
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Training Required yes no 0 Original issuance ,/
1 Reflects approval responsibility of fianager, Engineering /
Assurance Department
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2 Changes procedure for incorporating checklists 3 Changes " design process technical audit" to " design /
process review"
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NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL EAD-4 3
,,vte eact or Engineering Assurance Department Procedure 1 5 SUSJl ct OATE'BlutD Reporting of 6MM Design Process Review /Techni ;l Assessment Results 0"'1"*f-20-83 l R3 1.0 Purpose This procedure establishes the method for preparation, review and approval, and reporting of design process review / technical assessment results. lR3 2.0 Scope This procedure applies to all design process reviews and technical assessments lR3 performed by the Engineering Assurance Department.
3.0 References 3.1 Engineering Assurance Department Procedure EAD-5, Control of Design Pro- R3 cess Review and Assessment Records 3.2 Engineering Assurance Department Procedure EAD-7, Reporting and Disposi-tion of Action Items 4.0 Definitions None 5.0 Responsibilities 5.1 Manager, Engineering Assurance Department Reviews and approves the design process review / technical assessment lR3 i
report and forwards the report to the Vice President, Nuclear Engineering
& Construction 5.2 Vice President, Nuclear Engineering & Construction Reviews and approves the design process review / technical assessment lR3 report
! 5.3 Engineering Assurance Department engineer l Prepares the design process review / technical assessment report in accor- lR3 l dance with this procedure 6.0 Procedure 6.1 Preparation of review / assessment report Within thirty (30) days after the completion of the review / assessment, a R3 draft review / assessment report shall be prepared by the responsible Engi-neering Assurance Department engineer (s), according to the following l
format:
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NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL EAD-4 3
,n. e cl or Engineering Assurance Department Procedure 2 5 Suest C, CaitillutD Reporting of 616M Design Process Review / Technical Assessment Results Dat' t"'f,'E0-83 6.1.1 Review / assessment report cover sheet Each review / assessment report shall have a cover sheet (Attachment R3 7.1) that gives the title and dates of the review / assessment and provides for formal sign-offs.
6.1.2 Purpose and scope This section shall provide a description of the objectives and the extent of the review / assessment performed. It shall also specify q3 any special concerns being addressed in this review / assessment.
6.1.3 Identification of participants and reviewers This section shall list the name of the organization being reviewed / assessed and the names of the participants and reviewers.l R3 6.1.4 List of documents reviewed This section shall contain the title and the accompanying numeri-cal designation review and revision number of the documents used for the l R3
/ assessment.
6.1.5 Sumary of findings This section shall contain a sumary of review / assessment results lR3 and refer to pertinent sections for detailed observations and findings (e.g., Sections 6.1.6,6.1.9).
6.1.6 Methods used for review / assessment and observations lR3 This section shall contain the description of the method used for the review / assessment and detailed findings. lR3 6.1.7 Preventive / corrective action and conclusions This section shall sumarize the areas of concern requiring preventive / corrective action. The section shall also sumarize
! areas where the design has been found adequate.
6.1.8 Need for further review / assessment lR3 ,
If a final conclusion cannot be reached based on the documents i reviewed, or if this review / assessment points out the need for R3 l further review / assessment, this section shall contain a listing of I
those areas requiring further investigation.
6.1.9 Appendices The appendices shall contain the following documents:
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NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL EAD-4 3 T8TLE PAGE OF Engineering Assurance Department Procedure 3 5 SUSJE CT DATEIllutD Reporting of 6 14 M Design Process Review / Technical Assessment Results on't""g,a20-83 lR3 6.1.9.1 Copy of alternate calculations, if used 6.1.9.2 Any other pertinent documents The completed checklists and questionnaire shall be filed in the Engineering Assurance Department files as well as in the South TexasProjectRecordsManagementSystem(STPRMS)butneednotbe a part of the report.
6.2 Review, approval, and distribution of review / assessment report. lR3 The Manager, Engineering Assurance Department, shall review the draft review / assessment report and provide his coments to the responsible lR3 Engineering Assurance Department engineer within two (2) weeks. After incorporating these coments, the responsible Engineering Assurance Department engineer shall sign the cover sheet and submit the report to the Manager, Engineering Assurance Department, who shall indicate his approval by signing the cover sheet. The Manager, Engineering Assurance Department, shall submit the report to the Vice President, Nuclear Engi-neering & Construction, for his approval. After the review / assessment l P.3 report has been approved by the Vice President, Nuclear Engineering &
Construction, the responsible Engineering Assurance Department engineer shall prepare the associated action item forms as required by Engineering Assurance Department Procedure EAD-7, Reporting and Disposition of Action Items, and shall forward the review / assessment report together with the l R3 action item forms to South Texas Project Engineering, the Quality Assur-ance Department, and other organizations in accordance with Engineering Assurance Department Procedures EAD-5 and EAD-7.
7.0 Attachments 7.1 Review / assessment report cover sheet lR3 i
( 7.2 Procedure flow chart l
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NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL EAD-4 3 9'Tkt eaGE OF Engineering Assurance Department Procedure 4 5 SWSJE CT caig ellutD Reporting of 6-1r_p, 3
Design Process Review / Technical Assessment Results l R3 oste Effe fi}0-83 Attachment 7.1 Review / Assessment Report Cover Sheet lR3 Document NW$er Review / assessment subject: l R3 l D3 Date(s)ofreview/ assessment:
Prepared by: Date:
Prepared by: Date:
Approved by: Date:
Manager, Engineering Assurance Department Approved by: Date:
Vice President.
Nuclear Engineering & Constructiori 1
P20C '!O- "E'"0-t@WlTON Lile4TINC t. P0wt3 CO**f.NY NUCLEAR ENGINEERING & CONSTRUCTION PROCEDURES MANUAL EAD-4 3 TeTLt PAGt Of Engineering Assurance Department Procedure 5 5 Cait#85ptD SWSst CT Reporting of 6_18;_ R1 Design Process Review / Technical Assessment Results IR3 i
nat' t"*edla-20-83 Attachment 7.2 Procedure Flow Chart Eng'g Assurance Dept engineer prepares _
review /a ssessment report lR3 comunefits ii
!, Managar.
% Eng% assarance Dept. A reviews and approves
- report comuments yes
't Vice Presiderit.
- no b c Engig & Const, reviews and approves report f'
in n assors= e De,t prepares action items.
distributes action itees and report
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to to to to VP. STP Records OA 1 IIt&C 1
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