|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
Text
.
TVA EMPLOYEE CONCERNS REPORT NUMBER: 201.4(B)
SPECIAL PROGRAM
! . REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0
\ NON-RESTART .10STIFICATION
SUMMARY
TITLE: Standards and Guides o Policy and Practice on Utilization o Adequacy and Completeness PAGE 1 0F 2 l REASON FOR REVISION:
l PREPARATION PREPARED BY: ,
ll!
- b. A Y^ !^n 7
/0//8/66
. VSIGNATURE ' DATE REVIEWS
/ l
- V SIGNATURE / DATE "N @Whad' r
SIGNATURE ek/w DATE CONCURRENCES -
~
8701090484 861222 / /#
i CEG-H: -
y M! / O . PJ Jr/
SRP: 04 mb / ff J2 -//-%
/
SIGNATURE DATE DATE SIGNATUK*/
APPROVED BY:
[
oQ hh j /f-/8-80 N/A ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- S Secret ry's signature dentoes SRP concurrences are in files.
,;_ SEQUOYAH NUCLEAR PLANT k
ENGINEERING RELATED EMPLOYEE CONCERNS SPECIAL PROGRAM NON-RESTART JUSTIFICATION
SUMMARY
SUBCATEGORY / ELEMENT 201.4(B)
The issues identified in this element refer to possible programmatic deficiencies in the engineering design process.
The issues address misuse, and lack of use of both industry and TVA engineering standards and guides.
Items in this element are considered to be addressing those non-mandatory industry standards, and non-mandatory TVA engineering standards and guides. Such standards and guides are included as applicable in design output documents.
Procedures place the responsibility for application of these engineering standards and guides on the engineer (i.e., they are used or not as applicable to the design, at the discretion of the engineer).
jj This type of situation, if found to be valid, would represent a
.: programmatic deficiency that must be formally addressed as needed
, improvement in the design process.
However, full implementation of this improvement is not considered to be a requirement for plant restart, because the issues do not present a programmatic problem with specific safety-significance.
Items such as mandatory regulatory guides and mandatory industry standards will be addressed as restart items in element reports 204.4 and 201.3 where they are used in nuclear safety significant design criteria.
- ATTACHMENT
- List of Issues for Programmatic ELEMENT NO. 201.4(B)
Date: 10/05/86
.n; I '?
0211D - Page 2
. _ m . . __ _
r m
' )*'
4 'b. ,
d y
- SUBCATEGORY 201 - INCORPORATION OF REQUIREKNTS AND COPetITMENTS IN DESIGN 201.4 LIST OF PROGRAPeuTIC ISSUES
APPLICABLE EPFLOYEE CONCERNS SQN RESTART - NO DATE: 10/05/86 ELEENT DESCRIPTION Standards and Guides WI-85-100-019 WI-85-100-038 o Policy and Practice on Utilization - IN-86-259-X11 o Adequacy and Completness BNP-QCP-10.35-8-26-2 ELEMENT WHERE RE SPON-
!$5UES ADDRESSED SIBLE GENERAL APPROACH / METHODOLOGY FOR ELE E NT REPORT CONCERN NUMBER (S) 204.4 BW Issues 3 through 6 W1-85-100-038 1. Design / Installation Drawings do not Design / installation drawings always represent design requirements. Review engineering procedures and their 1.
do not always represent or references to guides and standards to determine include design requirements. 2. Design / Installation Drawings do not 204.4 BW which requirements are to be included on the Design guides / standards are always include design requirements. drawings, utilized only when designers want to use them. Design 3. Design Guides and Standards are 201.4 DZ
- 2. Establish examples of drawings from guides / standards are inadequate only used when desired by Designer. each discipline to be reviewed against design in many areas, and there are requirements, misuses, such as applicable 4. Design Guides and Standards are 201.4 DZ parts are not referenced or inadequate in many areas, Review drawings and evaluate.
3.
excerpted as requirements. CI 201.4 DZ has no further information. 5. Design Guides and Standards are Anonymous concern via letter. misused.
- 6. Applicable parts of Guides / 201.4 DZ Standards are not referenced or excerpted as requirements on drawings.
Engineering changes TVA standards 201.4 DZ !ssue 1 BNP-QCP-10.35-8-26-2 1.
Engineering can do a job within after the job is complete, perhaps The word standard is interpreted to mean because the completed job did not 1.
their standards, then they " criteria" or design basis, (i.e., a TVA change those standards after meet the original standards. Standard) since an industry standard cannot be the job is complete. changed by TVA.
- 2. Review appropriate " deviation" reports which
- - describe cases where standards were violated.
- 3. E.aluate magnitude of review findings back as far as start of original construction.
1 0897d-5
&j% , it "
rv t ?)* *
<_v 4 . _
SUBCATEGORY 201 - INCORPORATION OF REQUIREENTS AND C0 Pet! TENTS IN DESIGN '
ELEE NT NUMBER 201.4 LIST OF PROGRAF 9 ETIC ISSUES - ,
APPLICABLE ELEENT DESCRIPTION EpFLOYEE CONCERNS SON RESTART - NO DATE: 10/05/86 Standards and Guides WI-85-100-019 WI-85-100-038 o Policy and Practice on Utilization . IN-86-259-111 o Adequacy and Completness BNP-QCP-10.35-8-26-2 ELEENT bHERE RESPON-CONCERN NUMBER (5) ISSUES ADDRESSED SIBLE GENERAL APPROACH / METHODOLOGY FOR ELEENT REPORT WI-85-100-019 1. Electrical and other Engineering 201.4 02 Issues 1 through 4 ,
Electrical Standards and Standards are treated as guides only, Guides are treated as guides, 1. Review Engineering procedures to determine and are not incorporated in 2. Electrical and other Engineering 201.4 DZ how standards ar.d guides are to applied.
design critcria requirements. Standards are treated as guides only.
Electrical design criteria, 2. Has this issue been identified in prior where it exists, is not 3. Electrical and other Engineering 201.4' DZ evaluations (audits,INPOreport.)?
complete, is vague, and in Standards are not incorporated ir.
general is inadequate. CI Design Criteria. 3. Evaluate if option for use is given to designer.
has no further information.
Anonymous concern via letter. 4 Electrical and other Engineering 201.4 DZ Issues 5 through 8 Guides are not incorporated in Design Criteria. See element report 201.3
- 5. Electrical and other Engineering 201.3 DZ Design Criteria do not always exist.
! 6. Existing Electrical and other 201.3 DZ
.I Engineering Design Criteria are not
. always complete.
l
- 7. Existing Electrial and other 201.3 DZ Engineering Design Criteria are vague.
- 8. Existing Electrical and other 201.3 DZ Engineering Design Criteria are.
inadequate.
i i
k 0897d-6 .
i
- d. A3 *
%?
SUBCA tGURY 201 - INCORPORATION OF REQUIREMENTS AND COMMITMENTS IN DESIGN OY '
ELEE NT NUMBER 201.4 LIST OF PROGRAledTIC ISSUES .
APPLICABLE ELEMENT DESCRIPTION EMPLOYEE CONCERNS SON RESTART - NO DATE: 10/05/86 Standards and Guides WI-85-100-019 WI-85-100-038 o Policy and Practice on Utilization ,
IN-86-259-X11 o Adequacy and Completness BNP-QCP-10.35-8-26-2
~
ELEMENT WHERE RE SPON-CONCERN NUMBER (S) ISSUES ADDRESSED SIBLE GENERAL APPRDACH/ METHODOLOGY FOR ELEMENT REPORT IN-86-259-X11 1. TVA electrical procedures do not 201.4 DZ Issue 1 through 3 If TVA electrical procedures include IEEE standard do not include IEEE standards requirements or their 1. Implications is that concern is related only to requirements or their equivalent, therefore, numerous electrical procedures, however, we will examine equivalent, numerous problems problems can result. broader scope.
can result. Construction Dept. concern. CI has no 2. CI refers to IEEE requirements 213.4 ELEC. 2. Determine if these issues have been identified further information. No in particular. in any other prior review (i.e., QA Audit. INPO follow-up required. findings,etc.).
- 3. Other TVA Engineering procedures 201.4 DZ do not include industry standards 3. Review Design Baseline and Verification requirements. Program for Sequoyah Plant to see if program will adequately address this issue.
- 4. Do current procedures cover this issue to prevent recurrence of problem?
- 5. Coordinate response with Electrical group, element report 213.4 e
0897d-7 m.m m.
REFERENCE - ECPSI20J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE -
45
- FREQUENCY - REQUEST OFFICE OF NUCLEAR PONER RUN TIME - 12:57:19
() ONP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS) RUN DATE - 12/02/86 LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 20104 STANDARDS AND GUIDES
() S GENERIC KEYWORD A H APPL QTC/NSRS P , KEYHORD B CONCERN SUB R PLT BBSH INVESTIGATION S CONCERN KEYHORD C NUMBER CAT CAT D LOC FLQB REPORT R DESCRIPTION KEYNORD D
()
IN 259-X11 EN 20104 S HBN YYYY 1-85-545-HBN SR IF TVA ELECTRICAL PROCEDURES DO NOT PROCEDURES l T50149 EN 21304 K-FORM INCLUDE IEEE STD. REQUIREMENTS OR TH STANDARDS EIR EQUIVALENT, NUMEROUS PROBLEMS CA ELECTRICAL !
O N RESULT. CONSTRUCTION DEPT. CONCER GENERAL l N. CI HAS NO ADDITIONAL INFORMATION l
. NO FOLLOH-UP REQUIRED. ,
() QCP10.35-8-262 EN 20104 N BLN YYYY SR ENGINEERING CAN-DO A JOB-HITHIN THEI R STANDARDS, THEN THEY CHANGE THOSE REPORT STANDARDS AFTER THE JOB IS COMPLETE.
()
HI 100-019 EN 20103 S HBN YYYY SR ELECTRICAL STANDARDS AND GUIDES ARE STANDARDS T50212 EN 20104 REPORT TREATED AS GUIDES, AND ARE NOT INCOR DESIGN RELATED EN 21303 P0 RATED IN DESIGN CRITERIA REQUIREME ELECTRICAL
() NTS. ELECTRICAL DESIGN CRITERIA, NH ERE IT EXISTS, IS NOT COMPLETE, IS V GENERAL AGUE, AND IN GENERAL IS INADEQUATE.
CI HAS NO FURTHER INFORMATION. ANO O NYMOUS CONCERN VIA LETTER.
HI 100-038 EN 20104 S HBN YYYY SR DESIGN / INSTALLATION DRAMINGS DO NOT DRAHINGS T50213 EN 20106 REPORT ALHAYS REPRESENT OR INCLUDE DESIGN R NONCONFORMANCE
() EN 20404 EQUIREMENTS. DESIGN GUIDES / STANDARD ENGINEERING GENERAL S ARE UTILIZED ONLY HHEN DESIGNERS H ANT TO SUE THEM. DESIGN GUIDES /STAN DARDS ARE INADEQUATE IN MANY AREAS, O AND THERE ARE MISUSES, SUCH AS APPLI CABLE PARTS ARE NOT REFERENCED OR EX CERPTED AS REQUIREMENTS. CI HAS NO FURTHER INFORMATION. ANONYMOUS CONC O ERN VIA LETTER.
4 CONCERNS FOR CATEGORY EN SUBCATEGORY 20104 ._
() -
O O . _ _. _ _
- '~
O
() ,
b
_