Rev 0 to Instrumentation & Control Design:Panel to Equipment Distances, TVA Employee Concerns Special Program Element ReptML20236E613 |
Person / Time |
---|
Site: |
Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
---|
Issue date: |
01/06/1987 |
---|
From: |
TENNESSEE VALLEY AUTHORITY |
---|
To: |
|
---|
Shared Package |
---|
ML20236E191 |
List: |
---|
References |
---|
229.12(B), 229.12(B)-R, 229.12(B)-R00, NUDOCS 8710290284 |
Download: ML20236E613 (8) |
|
|
---|
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
n. - - -
- rii *
> .3 '.
'I
- TVA-EMPLOYEE CONCERNS REPORT NlNBER
- - 229.12(B) 9 LSPECIAL PROGRAM H ' REPORT TYPE: SEQUOYAH ELEMENT ' REVISION NUMBER: 0- 1
_1 i ;.
TITLE: INSTRUMENTATION AND CONTROL DESIGN Panel To Equipment Distances PAGE 1 0F-8 -
'i.
REASON FOR REVISION:
.]
1 d
i
,I J
l PREPARATION PREPARED BY:
// u d-e' k .SIGNATURE 5 : n ts ' h //r/S7 b
(' ' ~
/ AATE -j j
REVIEWS l
/- J';-fg
} '
7 ' '~ DATE
~ M SIGNATURE/ t TAS: 1 SIGNATURE DATE CONCURRENCE 5 ,
8710290284 871023 PDR ADOCK 05000327-
/,
i 73, . //48)<
P PDR CEG-H: TE N O N47 SRP: '
SIGNATURE DATE SIGNATURE DATE APPROVED BY:
DATE MANAGER OF NUCLEAR POWER DATE ECSP MANAGER CONCURRENCE (FINAL REPORT ONLY)
4 r~ 'TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.12(B)
) SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 2 0F 8 i
- 1. CHARACTERIZATION OF ISSUES:
Concern: Issues:
IN-85-068-606 a. Distances between control panels "HRC identified the following and controlled equipment are too concern from review of QTC file, long.
' A lot of instrument panels are "
located far away from the b. Distances between instrument racks /
equipment they control.'" panels and sensors are too long.
- c. Possible noncompliance ~ with FSAR !
commitments or NRC regulations.
The following issues related to this concern are addressed in other reports:
Human factors engineering of main and auxiliary control room (addressed in
'~
SQN Element Report 208.1).
480V power receptacles unsafe "
(addressed in SQN Element Report 235.1).
Hand switch location for maintenance (addressed in WBN Element Report 235.3). l
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES NO X Identified by Not applicable Date Not applicable
- 3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:
No specific locations or identification were given in the concern.
l l
- 4. INTERVIEW FILES REVIEWED:
l The working and expurgated ECTG files did not contain any t
information on this concern other than the K-form.
0617D - 01/05/87
4 TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.12(B)
SPECIAL PROGRAM REVISION NUMBER:' 0 PAGE 3 0F 8
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT. g 1
See Appendix A.
- 8. EVALUATION PROCESS:
- a. Clarified terminology of the concern.
- b. Investigated possible disadvantages of remote controls and the mitigating features.
- c. Surveyed SQN FSAR, NRC regulatory guides, TVA design criteria, and industry standards for limitations on distance of controls from equipment.
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS: ,
Chronology 1 08/08/86: Concern received by TVA.
Discussion: .
- a.
Background:
i This concern was originally raised on WBN and is considered applicable to SQN because of the basic similarity of the two plants and the general nature of the concern. NRC identified the concern from review of QTC files. The specific QTC files relating to this concern cou'd not be identified.
0617D - 01/05/87
i
'TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.12(B)
SPECIAL PROGRAM REVISION NUMBER: 0 .
PAGE 4 0F 8 TVA Design Guide ( App. A, 5.j) terminology disting'uishes between " control panel" and " instrument rack" or instrument ;
panel," the latter being wall mounted. The NRC's use of the i phrase "from the equipment they control," leads the evaluator primarily to the issue of " control panols" being too remote l fron the controlled equipment. However, the notion of remote
" instrument racks" or " instrument panels" resulting in 1ong !
sensing lines is also entertained as a presumed secondary- I issue. !
- b. Control Panels:
Centralized control of large plants with complex system interactions is a well established practice. Localized control is usually restricted to testing and maintenance ;
functions (e.g., setting of limit switches, breakers for i power disconnect, etc.). Travel time of electrical control signals is irrelevant for all hydraulic and thermodynamic ;
processes and mechanical equipment encountered. Process and q equipment response times are several orders of magnitude longer.
--(
Indicating instrumentation in the centralized control room makes visual observation of the controlled equipment unnecessary. Many process parameters are only detectable by sensors and would not be apparent to observation of the l equipment. j Visual observation is required in some instances (physical -i positioning). Where this is necessary but access is ]
restricted, closed circuit television (CCTV) or mirrors may l be employed (e.g., radwaste and irradiated fuel handling, !
containment survey). These are exceptions to the usual controls in nuclear power plants.
- c. Instrument Racks / Panels:
1 Instrument racks / panels containing transmitters are usually located as close as possible to the process being sensed.
Proper installation of liquid-filled instrument sensing (impulse) lines avoids the inclusion of compressible fluids.
The subcooled medium propagates the pressure signal at response times that are orders of magnitude shorter than the time it takes process variables to change.
For remote, liquid displacement type level instrumentation, the response time and sensing line length are considered in l the design.
0617D - 01/05/07
a c.
^
/ .TVA EMPLOYEE ~ CONCERNS- ' REPORT NUMBER: 229.12(B )
SPECIAL PROGRAM' REVISION NUMBER: 0- ;
.- , 1 PAGE 5 0F 8-1
. 4 Earlier' problems reported by Nuclear Plant Operating .
1 Experience Inc. ( App. A, 5.e), such as freezing of, or air and dirt.in sensing lines at SQN, have been corrected and ;
were not'due -to sensing line lengths as such. 1
- i. !
- d. Regulatory and TVA Requirements:
-l The . type of: controls required in the main and auxiliary control room for safe plant operation is described in FSAR - !
Section 7.0 ( App. A, 5.a). ~ Human Factor Engineering (HFE) i practices per TVA Design' Guides .( App.. A, 5.k,1, and m) and j NRC Reports ( App. A, 5.q and r) have been applied .to ensure operability. Verification of HFE compliance is confirmed by ECSP Report 208.1. ( App. A, 5.p).
NRC General Design Criterion 21 -( App. A, 5.d) requires j protective system designs which allow periodic testing. NRC.
Regulatory . Guide 1.22 ( App. A,. 5.f) and IEEE Standard . ;
338-1977 ( App. A, 5.1) require these tests to include the.
control system response times. These tests have been performed, and any response time deficiencies have been
( corrected. No TVA design criteria,: NRC regulatory guides, notices, . bulletins, or industry standards could be identified 1 that limit the. distance of controls or instruments from .
associated equipment or, sensors. The Nuclear Plant Operating !
Experience Inc. reports ( App. A, 5.e) were reviewed for 'l response time problems and none were found that'related to ]
line. length. t l
Findings: l
- a. TVA's instrument and control configuration is consistent with industry practice. For panels containing electrical controls and process parameter indications, no adverse effect on 1 response time or safe, efficient operation of equipment because of remoteness could be established. ,
I
- b. No adverse effects on response time with properly installed long liquid-sensing (impulse) lines could be established.
1 i
f 1
l
' 0617D - 01/05/87 1
4
.; t,
!TVA EMPLOYEE- CONCERNS :REPORT NIMBER: - 229.12(B )
SPECIAL PROGRAM .
REVISION NUMBER- 0. l
.PAGE 6 0F.~8
- c. No NRC, TVA, or industry regulation'or standard could be ,
-found which limits the distance between equipment and control panels / instrument racks numerically. NRC requires periodic testing of controls and instrumentation, including response time, of protective systems. These tests have been performed-
~
and .any,. deficiencies corrected.
Conclusion:
The concern is not valid for either electrical control panels or '
for instrument racks with liquid containing transmitters. No NRC or TVA regulation exists restricting the distance between controls or instruments and the equipment / process they control or sense. . 1 Physical observation of the equipment or process is not necessary [
for safe and efficient operation. No problems related to this' 1 concern have been reported. '.
1
' 10 ; CORRECTIVE-ACTION No corrective action is required.
'\
, t i
l p
K 0617D - 01/05/87
W',.
, + v i TVA EMPLOYEE CONCERNS REPORT NtMBER: 229.12(B)
SPECIAL PROGRAM' REVISION NUMBER': 0-f -
PAGE 7 0F'8 i i
APPENDIX A
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. SNP FSAR Section 7.0, Instrumentation and Controls, (04/14/83), through Amendment 3, (04/86)
. b. Instrument Society of America (ISA) Standards and Practices for Instrumentation, 8th edition,1986
- c. NRC Regulatory Guide 1.151, "Instrurent Sensing Lines," (July 1983) .
I
- d. 10CFR50, Appendix A, " General Design Criteria for Nuclear l Power Plants," (02/10/71) j
- e. Nuclear Power Plant Experience Inc.- Reports, published by-The S. M.- Stoller Corporation, up to October 1986 for SQN-01
- f. NRC Regulatory Guide 1.22, " Periodic Testing of Protection
- - Systems Actuation Functions," (02/17/72) j
- g. TVA ECSP, Element Report SQN 235.1(B), Preliminary, ,
" Electrical Safety, 480 V Power Receptacles Unsafe," l (11/24/86)
- h. TVA ECSP, Element Report WBN 235.3, " Electrical' Safety, Handswitch Location Violates Regulatory Requirements,"
(05/20/86) ,
- 1. Institute of Electrical and Electronics Engineers (IEEE) Std 338-1977, " Standard Criteria for the Periodic Testing of Nuclear Generating Station Safety Systems" ;
- j. TVA Electrical Design Guide DG-E1.1.3, " Clearance Around Electrical and Instrumentation and Control Equipment,"
(03/29/84)
- k. TVA Electrical Design Guide DG-E18.1.12, " Human Factors Engineering in Control Console, Cabinet, and Panel Layout,"
(04/30/82) ,
- 1. TVA Electrical Design Guide DG-E18.1.13 " Human Factors Engineering in Alarm Systems," (07/16/82)
- m. TVA Electrical Design Guide DG-E18.1.14, " Human Factors Engineering in Controls and Visual Displays," (04/30/82) 06170 - 01/05/87
1 3
- u. ,
1
'TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.12(B)
SPECIAL PROGRN4 l REVISION NUMBER: 0 i f PAGE 8 0F 8' l I
APPENDIX A (cont'd)
- n. TVA ECSP, Element Report SQN 225.1(B), "480 V Power Receptacles Unsafe"
- o. TVA ECSP, Element Report WBN 235.3, " Hand Switch Location for Maintenance"
- p. TVA ECSP, Element Report SQN 208.1(B), " Human Factors Review Program HUREG-0700"
- q. NRC Report NUREG 0700, " Guidelines for Control Room Design Review," (08/81)
- r. NRC Report NUREG 0737, " Clarification of TMI Action Plan Requirements" (11/80) and Supplement, (01/83)
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
- a. NRC Regulatory Guide 1.22
- b. IEEE Standard 338-1977
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
- a. Telephone call from P. Nesbitt, TVA, to L. Damon, Bechtel, IOM #287, (09/23/86)
- b. Telephone call from P. Nesbitt, TVA, to W. Blumer, Bechtel, IOM #501, (12/31/86) 0617D - 01/05/87
--_--