Rev 1 to TVA Employee Concerns Special Program Sequoyah Element Rept 210.1(B), Environ Qualification,Sensitive Instruments/Harsh EnvironsML20213A371 |
Person / Time |
---|
Site: |
Sequoyah |
---|
Issue date: |
01/22/1987 |
---|
From: |
TENNESSEE VALLEY AUTHORITY |
---|
To: |
|
---|
Shared Package |
---|
ML20213A334 |
List: |
---|
References |
---|
210.1(B), 210.1(B)-R01, 210.1(B)-R1, NUDOCS 8702030240 |
Download: ML20213A371 (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
- _ _ _ _ __. ..
a
- - TVA EMPLOYEE CONCERNS REPORT NLMBER: 210,1 (B)
SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NLMBER: 1
{
TITLE: ENVIR00 MENTAL QUALIFICATION Sensitive Instrianents/ Harsh Envirorments PAGE 1 0F 7 REASON FOR REVISION:
- 1. Revised to incorporate TVA consents; to add chronology; and to add Section 10, Corrective Action.
PRF,M RATION PREPARLD BY: ,
'} g ,g
(
" rad. 2k /fV G& th7//c7 DATE '
5 @ ATURE /
REVIEWS
.5E4A4 REVIEW IIIL y h y I 87 DATE p SIGNATURE [
\\ TAS y [0 SIGNATURE DATE l CONCURRENCES
/WO f
/kh7' s
Nm CEG-H: Wo UW d'f/-7 F7 ES SRP: kmSIG3AlURE*
buk 1-21-87 DATE SIGNATURE DATE APPROVED BY' Ok ../ /-72 8[ N/A O MANAGER OF NUCLEAR POWER DATE ECSPMAMGER DATE
{E, CONCURRENCE (FINAL REPORT ONLY)
- SRI' Secretary's signature denotes SRI' concurrencen are in filen.
A
(
. TVA EMPLOYEE CONCERNS REPORT NUMBER: 210.1 -(B)
. SPECIAL PROGRAM REVISION NUMBER: 1 ',
b PAGE 2 0F 7 1
r
- 1. CHARACTERIZATION OF ISSUE (S): ,
Concern: Issue: s Certain sensitive equipment :
IN-85-068-002
" Sensitive equipment, i.e. , such as instruments and instrument instruments and instrument panels, is located in a harsh .
panels are located in a harsh environment near the lower portion environment. CI stated that the of the reactor.
location of this equipment is in the bottom of the reactor and ,
part way up the building. Unit not specified."
- 2. HAVE ISSUE (S) BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES NO X 4 Identified by Not App 1tcable i
Date Not Appifcable .
( Documentation Identifiers:
Not Applicable l
- 3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IRNIIPICATIUN3 STAILU IN ELtmMI.
Sensitive instrumentation in reactor building areas.
- 4. INTERVIEW FILES REVIEWED:
IN-85-068 No additional infonnation resulted from review. l S. DOCLMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
0027D - 01/07/87
~
TVA EMPLOYEE CONCERNS REPORT NIMBER: 210,1 (B)
,/,, ,
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 3 0F 7
- 6. ' WHAT REGULATIONS, LICENSING C0194ITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
- See Appendix A.
LISTc REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER 7.
UITCllSSIONS-RELATED TO ELEMENT.
See Appendix A.
- 8. EVALUATION PROLES S_S1
- a. Reviewed progress and development of the Special Program on l Environmental Qualification outlined in the Sequoyah Nuclear s
Perfomance Plan (Section III, Part 1.0) to establish that this specific issue is being or has been addressed.
- b. Identified and reviewed any investigative reports that may l currently be in progress on this subject and any corrective O action taken. Established adequacy of same. l
- c. Based upon the applicability of the documentation developed in Steps a and b above, resolved this specific concern by the following program:
o Established parameters of what constitutes a " harsh" l environment in accordance with 10CFR50.49 and Regulatory Guide 1.89 s
' Io located such enviroments on Sequoyah Equipment Location l Drawings o Identified enviromentally sensitive equipment in these l areas o Reviewed sample Enviromental Qualification reports l gemane to Sequoyah to confirm that the issue has been adequately addressed t
00270 - 01/07/87
r TVA EMPLOYEE CONCERNS REPORT NUMBER: 210.1 (B) 1- SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 4 0F 7
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS Chronology:
07-08/85: TVA managemer.t reviewed equipment qualification program at SQN 09/25/85: WesTec/TVA issued report entitled " Management Review of Environmental Qualification Activities and Documentation for Compliance with 10CFR50.49" 11/06/85: TVA received employee concern 11/18/85: TVA issued SQN Standard Procedures SQA 173, "SQN 10CFR50.49 Environmental Qualification Program," R1 11/30/85: Date specified by NRC for full compliance with 10CFR50.49 03/12/86: NSRS issued Investigative Report I-85-225-SQN, "Enviromental Qualification / Electrical /I&C Equipment / Components" 08/15/86: NRC issued report on Inspection Nos. 50-327/86-01 and '
50-328/86-01 on SQN EQP 09/11/86: TVA issued " List of Devices Inside Contaiment 2nd Lower Compartment" for SQN 09/15/86: TVA issued "IE Electrical Equipment Requiring q Qualification Under 10CFR50.49 List," R4 Discussion:
While the comern does not mention or establish that safety-related equipment is involved, the evaluator presumes that this is what was meant. Further, the relative tenn " sensitive instrumentation" is not defined as a special category of equipment in any of the regulatory requirements, nor are any unique qualification parameters stipulated. In this review the 10CFR50.49 words
" electric equipment important to safety" were taken to include the
" sensitive equipment" referred to in the concern. The following response proceeds on the basis of these presumptions.
10CFR50.49 specifically excludes mild environments which it defines as:
"an enviroment that would at no time be significantly more severe than the environment that would occur during nomal plant operation, including anticipated operational Occurrences."
e L 0027D - 01/07/87
s TVA EMPLOYEE CONCERNS- REPORT NtMBER: 210.1 (B)
/. SPECIAL PROGRAM
- l. PAGE 5 0F 7 What constitutes a " harsh environment" is not as explicitly defined; rather, it is presuned to be one that would be significantly more severe at some point in time as compared to nonnal plant operations .
including anticipated occurrences. In addressing this specific concern, the evaluator applied this meaning to the Concerned Individual's (CI's) use of the words " harsh environment."
It should be noted that none of the regulatory requirements listed in Appendix A prohibit equipment, including " sensitive instrunentation,"
fran being placed in harsh environments. These requirements only stipulate that when safety-related electrical equipment is placed in such environnents, it must be appropriately qualified.
The subject of Environmental Qualification Program (EQP) adequacy was l validly raised by other concerned individuals and addressed in Element Report 210.2 which concludes that:
"These concerns have been independently validated by the findings of the joint WesTec/TVA task force. This is consistent with NSRS Report I-85-225-SQN which addressed these concerns. The corrective actions listed in NSRS Report I-85-225-SQN as augnented by the complete EQ Program outlined in the SQN Nuclear Perfonnance Plan . . . should be sufficient l to properly resolve the issues validly stipulated by these Concerned Individuals."
The area specifically referred to in the Concern ("the bottom of the l reactor and part way up the building") contains flow, pressure, and l
level transmitters, motor operated flow control valves, position switches, temperature elements, and the associated wire and cable.
All of this equipment that is important to safety either has been or is in the process of being qualified as outlined in Element Report 21 0.2. The evaluator could not identify any special or " sensitive" instrumentation in these areas that was not being so addressed.
Findings:
The concern does not specifically identify any safety-related equipeent of a unique or " sensitive" nature that is not already being covered in the SQN EQP. The areas in question can be considered
" harsh." Therefore, safety-related instrumentation in these areas l' must be appropriately qualified. The SQN EQP presently in place adequately covers the equipment located in the areas referred to by l
the CI and as more accurately identified by Sheets 44 to 48 of SQN I Drawing 47E235, "Environnental Data, Environment - Harsh," and l "Sequoyah Nuclear Plant - Units 1 and 2, Equipment Requiring l Qualification under 10CFR50.49 List."
.-(.
i 0027D - 01/07/87
- TVA EMPLOYEE CONCERNS REPORT NUMBER:. 210.1 (B)
' '. SPECIAL PROGRAM REVISION NUMBER: 1
( PAGE 6 0F 7
Conclusions:
The concern is valid in that sensitive instrumentation is located in the areas described. However, this fact is known and appropriate measures have been taken to ensure operability of this equipment in spite of the environmental conditions that exist. The present SQN EQP is adequate to cover safety-related equipment located in the areas identified by the concern. l
- 10. CORRECTIVE ACTION No corrective actioit is required.
1 i
h l
1 I
00270 - 01/07/87 f
TVA EMPLOYEE CONCERNS REPORT NUMBER: 210.1 (B)
'- SPECIAL PROGRAM REVISION NLNBER: 1 PAGE 7 0F 7 APPENDIX A
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. TVA Employee Concerns Special Program, Element Report 210.2, "Enviromental Qualification Program"
- b. TVA Drawing 47E235, Sheets 44, 45, 46, 47, and 48,
" Environmental Data, Enviroment - Harsh" l
- c. 10CFR50.49, "Enviromental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants"
- d. U.S. NRC NUREG 0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," R1
- e. U.S. NRC Regulatory Guide 1.89, "Enviromental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," R1, (06/84)
I
- f. IEEE STD 323-1974, "IEEE Standard for Qualifying Class lE Ig Equipment for Nuclear Power Generating Stations," (02/24/74)
- g. List of Devices Inside Contaiment 2nd Lower Compartment, (09/11/86) l
- h. Sequoyah Nuclear Plant Units 1 and 2, "lE Electrical Equipment Requiring Qualification Under 10CFR50.49 List," R4, (09/15/86) l l 6. WHAT REGULATIONS, LICENSING COM ITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
L a. 10CFR50.49, "Enviromental Qualification of Electrical l Equipment Important to Safety for Nuclear Power Plants"
- b. U.S. NRC Regulatory Guide 1.89, "Enviromental Qualification of Certain Electric Equipment Important to Safety for Nuclear L
Power Plants," R1, (06/84)
I I c. U.S. NRC NUREG 0588, " Interim Staff Position on Environmental
! Qualification of Safety-Related Electrical Equipment," R1
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
RFI-504/TVA Transmittal 110
[ 0027D - 01/07/87 l
-. ._, ..- . .~
^
N, O O ...
- 9. .
PAGE -
72 REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY RUN TIME - 12:57:19 FREQUENCY - REQUEST OFFICE OF NUCLEAR POWER RUN DATE - 12/02/86 g
ONP - 1555 - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS)
LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 21001 SENSITIVE EQUIPMENT LOCATED IN HARSH ENVIRONMENT KEYHORD A S GENERIC KEYHORD B H APPL QTC/NSRS P CONCERN KEYHORD C CONCERN SUB R PLT BBSH INVESTIGATION S KEYHORD D HUMBER CAT CAT D LOC FLQB REPORT R DESCRIPTION y
SS SENSITIVE EQUIPMENT, IE INSTRUMENTS DESIGN PROCESS IN 068-002 EN 21001 N HBN NNYY INSTALLATION T50186 REPORT AND INSTRUMENT PANELS ARE LOCATED IN I
A HARSH ENVIRONMENT. CI STATED THA INSTRUMENTATION
- l. T THE LOCATION OF THIS EQUIPMENT IS DEVICES
)
] IN THE BOTTOM OF THE REACTOR AND PAR T HAY UP THE BUILDING. UNIT NOT SPE CIFIED. CONSTRUCTION DEPT. CONCERN.
t i-CI COULD NOT PROVIDE ANY SPECIFICS
/ DETAILS.
I 1 CONCERNS FOR CATEGORY EN SUBCATEGORY 21001
}
)
I
.i t .
me e
j 3
a