|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20212C2811999-09-13013 September 1999 Safety Evaluation Supporting Amends 116 & 104 to Licenses NPF-76 & NPF-80,respectively ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211P9001999-09-0202 September 1999 Safety Evaluation Supporting Amends 115 & 103 to Licenses NPF-76 & NPF-80,respectively ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20211F3651999-08-19019 August 1999 Safety Evaluation Supporting Amends 114 & 102 to Licenses NPF-76 & NPF-80,respectively ML20210K4881999-08-0303 August 1999 Safety Evaluation Supporting Amends 113 & 101 to Licenses NPF-76 & NPF-80,respectively ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20196K7091999-07-0202 July 1999 Safety Evaluation Supporting Amend 100 to License NPF-80 ML20212J0031999-06-23023 June 1999 Safety Evaluation Supporting Amends 112 & 99 to Licenses NPF-76 & NPF-80,respectively ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20206U7731999-05-20020 May 1999 Safety Evaluation Supporting Amends 110 & 97 to Licenses NPF-76 & NPF-80,respectively ML20207A1101999-05-17017 May 1999 Safety Evaluation Supporting Amends 109 & 96 to Licenses NPF-76 & NPF-80,respectively ML20206A1411999-04-19019 April 1999 Safety Evaluation Supporting Amends 107 & 94 to Licenses NPF-76 & NPF-80,respectively ML20206A3611999-04-19019 April 1999 Safety Evaluation Supporting Amends 108 & 95 to Licenses NPF-76 & NPF-80,respectively ML20205Q6771999-04-16016 April 1999 Safety Evaluation Supporting Amends 105 & 92 to Licenses NPF-76 & NPF-80,respectively ML20205Q7321999-04-16016 April 1999 Safety Evaluation Supporting Amends 106 & 93 to Licenses NPF-76 & NPF-80,respectively ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 ML20207L2361999-03-0303 March 1999 Safety Evaluation Supporting Amends 104 & 91 to Licenses NPF-76 & NPF-80,respectively ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20203B5221999-02-0808 February 1999 Safety Evaluation Supporting Amends 102 & 89 to Licenses NPF-76 & NPF-80,respectively ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20199H7811999-01-21021 January 1999 Safety Evaluation Supporting Amends 101 & 88 to Licenses NPF-76 & NPF-80,respectively ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 ML20198B3491998-12-15015 December 1998 Safety Evaluation Accepting Relief Request to Use ASME Section XI Code Cases 2142-1 & 2143-1 for Replacement SGs ML20198B4111998-12-15015 December 1998 Staff Evaluation Rept of Individual Plant Exam of External Events (IPEEE) Submittal on South Texas Project,Units 1 & 2 ML20195J0161998-11-18018 November 1998 Safety Evaluation Supporting Amends 99 & 86 to Licenses NPF-76 & NPF-80,respectively ML20195J5331998-11-18018 November 1998 Safety Evaluation Supporting Amends 100 & 87 to Licenses NPF-76 & NPF-80,respectively ML20195B9601998-11-0606 November 1998 Safety Evaluation Accepting Proposed long-term C/As for Assuring Operability of MSSVs ML20195C8581998-11-0505 November 1998 SER Accepting Order Approving Application Re Proposed Corporate Merger of Central & South West Corp & American Electric Power Co,Inc ML20154N3371998-10-15015 October 1998 Safety Evaluation Re Licensee Request for Deviation from Fire Protection Program Incorporating Requirements of Section III.G.2.c of 10CFR50,App R ML20154B9531998-09-29029 September 1998 Safety Evaluation Supporting Amends 97 & 84 to Licenses NPF-76 & NPF-80,respectively ML20153F9751998-09-24024 September 1998 Safety Evaluation Supporting Amends 95 & 82 to Licenses NPF-76 & NPF-80,respectively ML20237D4931998-08-21021 August 1998 Safety Evaluation Approving Request to Use ASME Section XI Code Case N-498-1 at STP ML20237D5281998-08-21021 August 1998 Safety Evaluation Re Proposed Increase in Sf Pool Heat Loads for Plant ML20249A1831998-06-11011 June 1998 SER Accepting Request for Temporary Relief from ASME Code, Section XI Requirements,To Repair Flaws in Essential Cooling Water Sys Piping ML20217Q6881998-05-0606 May 1998 Safety Evaluation Accepting Monitoring for Leakage in Normal & Alternate Charging & Auxiliary Spray Lines at STP ML20216D4721998-03-11011 March 1998 Safety Evaluation Supporting Amends 94 & 81 to Licenses NPF-76 & NPF-81,respectively ML20199D0251997-11-17017 November 1997 SER Accepting Relief Requests for Inservice Testing Program for Pumps & Valves ML20199C8471997-11-17017 November 1997 Safety Evaluation Supporting Amends 93 & 80 to Licenses NPF-76 & NPF-80,respectively ML20199B2751997-11-0606 November 1997 Safety Evaluation Accepting Methodology for Graded QA Initiative in Operations QA Description for Plant ML20212C4721997-10-20020 October 1997 Safety Evaluation Supporting Amends 92 & 79 to Licenses NPF-76 & NPF-80,respectively ML20211G2271997-09-23023 September 1997 Safety Evaluation Supporting Amends 91 & 78 to Licenses NPF-76 & NPF-80,respectively 1999-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) 05000498/LER-1999-008, :on 990912,unit Tripped During Performance of Main Turbine Emergency Trip Test Procedures.Caused by Failure in Turbine Trip Test Circuitry.Main Control Boards Were Cleaned & Other Panels Were Inspected1999-10-12012 October 1999
- on 990912,unit Tripped During Performance of Main Turbine Emergency Trip Test Procedures.Caused by Failure in Turbine Trip Test Circuitry.Main Control Boards Were Cleaned & Other Panels Were Inspected
ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr 05000499/LER-1999-006-01, :on 990901,TS 3.0.3 Entered.Caused by Insufficient Procedural Guidance for Use of TS 3.0.6.SG 2D low-level Channel 2 Input Relay to ESF Actuation Logic Circuitry Replaced on 9909011999-09-30030 September 1999
- on 990901,TS 3.0.3 Entered.Caused by Insufficient Procedural Guidance for Use of TS 3.0.6.SG 2D low-level Channel 2 Input Relay to ESF Actuation Logic Circuitry Replaced on 990901
NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr 05000499/LER-1999-005-01, :on 990824,ESFA Following Loss of Power to Standby Transformer 2 Was Noted.Internal Fault Caused C Phase Arrester Failure.Replaced All Surge Arresters for Standby Transformer 21999-09-20020 September 1999
- on 990824,ESFA Following Loss of Power to Standby Transformer 2 Was Noted.Internal Fault Caused C Phase Arrester Failure.Replaced All Surge Arresters for Standby Transformer 2
ML20212C2811999-09-13013 September 1999 Safety Evaluation Supporting Amends 116 & 104 to Licenses NPF-76 & NPF-80,respectively 05000498/LER-1999-007, :on 990812,plant Train B CR Makeup & Cleanup Filtration Sys Was Declared Inoperable for Greater than Aot. Caused by Degradation of Makeup Filter & Filter Charcoal Due to Aging.Subject Filter Was Replaced on 9908051999-09-13013 September 1999
- on 990812,plant Train B CR Makeup & Cleanup Filtration Sys Was Declared Inoperable for Greater than Aot. Caused by Degradation of Makeup Filter & Filter Charcoal Due to Aging.Subject Filter Was Replaced on 990805
ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 ML20211P9001999-09-0202 September 1999 Safety Evaluation Supporting Amends 115 & 103 to Licenses NPF-76 & NPF-80,respectively NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20211F3651999-08-19019 August 1999 Safety Evaluation Supporting Amends 114 & 102 to Licenses NPF-76 & NPF-80,respectively ML20210K4881999-08-0303 August 1999 Safety Evaluation Supporting Amends 113 & 101 to Licenses NPF-76 & NPF-80,respectively ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210D4491999-07-21021 July 1999 Revised Chapters to Operations QA Plan, Including Rev 9 to Chapter 1.0, Organization & Rev 6 to Chapter 16.0, Independent Technical Review ML20210D4821999-07-21021 July 1999 1RE08 ISI Summary Rept for Steam Generator Tubing of South Texas Project Electric Generating Station Unit 1 NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With1999-07-15015 July 1999 LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20216D7481999-07-0707 July 1999 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1 ML20196K7091999-07-0202 July 1999 Safety Evaluation Supporting Amend 100 to License NPF-80 NOC-AE-000593, Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With1999-06-28028 June 1999 LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With ML20212J0031999-06-23023 June 1999 Safety Evaluation Supporting Amends 112 & 99 to Licenses NPF-76 & NPF-80,respectively ML20196G5821999-06-23023 June 1999 LER 99-S02-00:on 990601,failure to Maintain Positive Control of Vital Area Security Key Was Noted.Caused by Lack of Attention to Detail.Discussed Event with Operator Involved IAW Constructive Discipline Program ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval 05000498/LER-1999-004-01, :on 990516,Unit 1 Experienced Automatic Reactor Trip.Caused by Equipment Failure.Stp Will Evaluate Potential Transformer Testing Procedure for Incorporation of Fuse Resistance Measurements by 990715.With1999-06-15015 June 1999
- on 990516,Unit 1 Experienced Automatic Reactor Trip.Caused by Equipment Failure.Stp Will Evaluate Potential Transformer Testing Procedure for Incorporation of Fuse Resistance Measurements by 990715.With
ML20196A2391999-06-15015 June 1999 Change QA-042 to Rev 13 of Operations QAP, Reflecting Current Organizational Alignment for South Texas Project & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-000563, Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with ML20206U7731999-05-20020 May 1999 Safety Evaluation Supporting Amends 110 & 97 to Licenses NPF-76 & NPF-80,respectively ML20206U5411999-05-18018 May 1999 Non-proprietary Errata Pages for Rev 2,Addendum 1 to WCAP-13699, Laser Welded Sleeves for 3/4 Inch Diamete Tube Feedring Type & W Preheater SGs Generic Sleeving Rept ML20207A1101999-05-17017 May 1999 Safety Evaluation Supporting Amends 109 & 96 to Licenses NPF-76 & NPF-80,respectively ML20206A7721999-04-30030 April 1999 STP Electric Generating Station Unit 1 Cycle 9 Colr NOC-AE-000543, Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with 05000498/LER-1999-003-01, :on 990329,CR HVAC Was Placed in Recirculation Mode of Operation Instead of Recirculation Mu Filtered Mode. Caused by Inadequate Verbal Communications.Briefed Crews on Attention to Detail During three-way Communications1999-04-29029 April 1999
- on 990329,CR HVAC Was Placed in Recirculation Mode of Operation Instead of Recirculation Mu Filtered Mode. Caused by Inadequate Verbal Communications.Briefed Crews on Attention to Detail During three-way Communications
05000498/LER-1999-002-01, :on 990327,inadequate Performance of TS Surveillance When Evaluating Source Range Nuclear Instrument Discriminator Bias Curve Results,Was Discovered.Caused by Lack of Process to Incorporate Info.Compared Bias Curves1999-04-26026 April 1999
- on 990327,inadequate Performance of TS Surveillance When Evaluating Source Range Nuclear Instrument Discriminator Bias Curve Results,Was Discovered.Caused by Lack of Process to Incorporate Info.Compared Bias Curves
ML20206A1411999-04-19019 April 1999 Safety Evaluation Supporting Amends 107 & 94 to Licenses NPF-76 & NPF-80,respectively ML20206A3611999-04-19019 April 1999 Safety Evaluation Supporting Amends 108 & 95 to Licenses NPF-76 & NPF-80,respectively ML20205Q6771999-04-16016 April 1999 Safety Evaluation Supporting Amends 105 & 92 to Licenses NPF-76 & NPF-80,respectively ML20205Q7321999-04-16016 April 1999 Safety Evaluation Supporting Amends 106 & 93 to Licenses NPF-76 & NPF-80,respectively 05000498/LER-1999-001-01, :on 990311,RHR Sys Was Found in Condition Outside Design Basis.Caused by Inadequate Implementation of Design Basis Requirements.Condition Remedied by Opening Disconnect Switches Per Rev to Plant Procedures1999-04-12012 April 1999
- on 990311,RHR Sys Was Found in Condition Outside Design Basis.Caused by Inadequate Implementation of Design Basis Requirements.Condition Remedied by Opening Disconnect Switches Per Rev to Plant Procedures
NOC-AE-000507, Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with 1999-09-09
[Table view] |
Text
, - - _ _.- - -.
.-... ~..
$n ce
^
1
- UNITED STATES g
j j
NUCLEAR REGULATORY COMMISSION
(
WASHINGTON, D.C. sese6 eeM
\\.....
};
SAFETY EVALUATION BY THE'0FFICE OF NUCLEAR REACTOR REGULATION 0F THE FIRST TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN I
REQUEST TO USE ASME SECTION XI CODE CASE N-546 j
HOUSTON LIGHTING AND POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL-POWER AND LIGHT COMPANY t
CITY OF AUSTIN. TEXAS i
SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
I The Technical Specifications for the South Texas Project, Units 1 and 2 (STP),
i state that the inservice inspection and testing of the American Society of Mechanical Engineers- (ASME) Code Class 1, 2,.and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1).
10 CFR 50.55a(a)(3) states that alternatives to the i'
requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission, if (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a l
compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components
'(including supports) shall meet the requirements, except the design and access p
provisions and the preservice examination requirements, set forth in the i4SME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant a
Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests
-conducted during the first ten-year interval and subsequent intervals comply
'with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference..in_10 CFR 50.55a(b) on the date twelve months prior to the start of the'120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the~ASME Code for STP during the first ten-year inservice inspection (ISI) interval is the 1983 Edition though the Summer 1983 Addenda.
l The components _(including supports) may meet the requirements set forth in 1
4 9705150030 970512
-PDR-ADOCK 05000498 ENCLOSURE G
PDR 4
o_,
c,
m.
subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated February 24, 1997, Houston Lighting and Power, the licensee requested approval for the implementation of the alternative rules of ASME Section XI Code Case N-546 dated August 24, 1995, titled " Alternative Requirements for Qualification of VT-2 Examination Personnel,Section XI, Division 1," pursuant to 10 CFR 50.55a(a)(3)(i) in lieu of the requirements of IWA-2300 to the ISI program for STP.
The staff has reviewed and evaluated the licensee's request and supporting information to use Code Case N-546 as a proposed alternative to the Code requirements for STP.
2.0 DISCVSSION A.
Reauest 4 r Authorization to Implement Alternatives to Code Reauirements Contained in Code Case N-546. Alternative Reauirements for Ovalification of VT-2 Visual Examination Personnel Code Reauirement:
The ASME Code Section XI, 1983 Edition including addenda through the Summer 1983, Subsection IWA-2300, " Qualification of Nondestructive Examination Personnel" requires that all personnel performing VT-2 visual examinations be certified to comparable levels of competency defined in ANSI N45.2.6-1973.
The VT-2 visual examination is conducted in accordance with ASME Code,Section XI, paragraph IWA-2212 and subarticle IWA-5240 to locate l
evidence of leakage from pressure retaining components, or abnormal leakage from components with or without leakage collection system, as required, during the conduct of pressure testing.
Licensees' Code Relief Reauest: The licensee has requested approval to implement alternatives to the Code requirements contained in Code Case N-546, Alternative Requirement for Qualification of VT-2 Examination Personnel, which is not yet approved by the NRC by reference in Regulatory Guide (RG) 1.147.
J i
i i
a <
B.
Licensees' Basis'for Reauestina Relief (as stated):
"As stated in Code Case N-546, " Alternate Requirements for Qualification of VT-2 Examination Personnel,Section XI, Division 1," plant personnel (e.g.,
i licensed and non-licensed operators, system engineers, testing technicians) with the specified training and plant walkdown experience need not be qualified nor certified to comparable levels of competence in accordance with j
ANSI N45.2.6.
Experience in identifying equipment problems and knowledge of 3
operating conditions will enhance the ability of plant personnel to locate leakage during VT-2 examination. With the specified'four hours of training on Section XI requirements and plant specific procedures for VT-2 examinations, i
the designated plant personnel will understand how leaks should be identified and documented and be fully capable of performing VT-2 examinations.
Qualifying personnel f'or VT-2 examinations under Code Case N-546 is less burdensome than qualifying and maintaining the present VT-2 certification.
i Adopting this Code Case makes it feasible to train more people to perform these tasks.
Furthermore, using personnel who are already required to perform functions in the plant will reduce the number of people required to enter into areas that may be radiologically restricted, resulting in fewer plant workers 1
exposed to potential radiation dose and keeping radiation exposure as low as j
reasonably achievable, j
Additionally, use of on-shift personnel will improve the process of returning systems to service.
Prompt return to service of safety tystems will improve the safety of the plant and the public."
i I
Licensees' Proposed Alternative to Code Reauirements (as stated):
" Code Case N-546 is to be used as an alternative to IWA-2300 as the basis for selecting personnel to perform VT-2 visual examination.
Plant personnel with the training and walkdown experience specified in Code Case N-546 need not be qualified nor certified to comparable levels of competence in accordance with ANSI N45.2.6.
In accordance with Code Case N-546, examination personnel will be qualified by the following:
)
At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> plant walkdown experience At least four hours of training on Section XI requirements and plant specific procedures for VT-2 visual examination, and Vision test requirements of IWA-2321, 1995 Edition i
l-1 The STP will comply with the requirements specified in Code Case N-546 l
assuring that VT-2 examinations are performed by appropriately trained and experienced personnel. This alternative provides an acceptable level of i
quality and safety as directed by 10 CFR 50.55a(a)(3)(i)."
l l
l
u 4
e <
3.0 EVALUATION AND CONCLUSION The Code requires that VT-2 visual examination personnel be qualified to comparable levels of competency as defined in ANSI N45.2.6. The Code also i
requires that the examination personnel be qualified for near and far distance vision acuity. -The licensee however, proposes to. implement the Code Case i
N-546 as an alternative to the requirements of IWA-2300 for qualification of VT-2 visual examination personnel which states the following:
i a.
"At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> plant walkdown experience, such as that gained by licensed and nonlicensed operators, local leak rate personnel, system engineers, and inspection and nondestructive examination personnel."
b.
"At least four hours of training on Section XI requirements and plant specific procedures for VT-2 visual examination."
i c.
" Vision test requirements of IWA-2321, 1995 Edition."
The staff believes that the qualification requirements in Code Case N-546 are comparable to those of the ASME Code,Section XI, paragraph IWA-2300 for VT-2 visual examination personnel.
In regard to selection of personnel to conduct the' test, the Code Case in. item (a) above, states that licensed and non-I licensed operators, local leak rate personnel, system engineers, and inspection and nondestructive examination personnel are eligible due to their plant experience. Typically, these professionals have sound working knowledge i
of plant components and piping layouts. Hence, they make good candidates for performing VT-2 visual examinations.
Furthermore, the licensee follows plant specific procedures. to obtain consistent VT-2. visual examination results even with the varied experience levels and potentially different leakage interpretations by employees performing the VT-2 visual examinations. The Code Case further requires a vision test for examination personnel similar to i
that of the Code.
Based on staff's review of Code Case N-546, it is concluded that the alternatives to the Code qualification requirements for examination personnel will provide an acceptable level of quality and safety in that it will. provide adequate leakage detection. Therefore, the licensee's request to implement i
i alternatives contained in Code Case N-546 is authorized pursuant to 10 CFR.50.55a(a)(3)(i) for the current interval until such time as the Code Case is approved by reference in RG 1.147. At that time, if the licensee intends to continue to implement this Code Case, the licensee must follow all provisions in Code Case N-546 with the limitations issued in RG 1.147, if any.
Principal Contributor:
P. Patnaik Date:
May 12, 1997 1
3 i
,m_.-
.r9
_.,.. -,,,.,