ML20126M509
| ML20126M509 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/22/1981 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15222A067 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8106190024 | |
| Download: ML20126M509 (61) | |
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.~9 ENVIRONMENTAL QUALIFICATION OF SAFETY-REIATED ELECTRIQAL EQUIPMENT IEB 79-01B TECHNICAL EVALUATION REPORT
. DOCKET NO. 50-270 PLANT: Oconee 2 R1 DATED: Novenber 18, 1980 e
Licensee: Duke Power Co:rpany Type Reactor: Babcock and Wilcox PWR , 1 l i ! Prepared by: Virgil L. Brown ee l UA N'# Engineering Support Section l Reactor Construction and Engine'ering Support Branch, RII ts/ //- /5'- Yb R1 Reflec y Duke Power Company's y l 11/1/80, Revision 5 Submittal. L . 81061900 h
TABLE OF CONTENTS PAGE NO.
- 1. INTRODUCTION ...................................................... I 1.1 General .................................................... I
- 2. BACKGROUND AND DISCUSSION ......................................... 1 2.1 General .................................................... 1 2.2 On-Site I'nspection ......................................... 2 2.3 Evaluation of Licensee's Report ............................ 2
- 3. GENERAL INFORMATION ...s........................................... 3
- 3.1 Identification of Class IE Electrical Systems............... 3 3.2 Service Conditiens ......................................... 3 3.3 Qualification Docamentation ................................ 4
- 4. EQUIPMINT DATE REVIEW ............................................. 4 s
4.1 Qualified Equipment ........................................ 4 4.2 Equipment With Aging Less Than Plant Life .................. 4 4.3 Equipment to be Replaced, Modified, or Relocated - Licensee Identified ................................................. 4 4.4 Equipment with Unresolved Qualification Items .............. 4 4.5 Equipment Not Qualified .................................... 5 4.6 Outstanding Items - Licensee Identified .................... 5 i
. .. . '4 . 7. Discussion of On-Site Inspection ........................... 5
- 5. CONCLUSIONS ....................................................... 5 i Attachment 1 Review Tabulation Sheets Used in Evaluation of Licensee's i Report l A,ttachment 2 List of Standard Systems '
Attachment 3 List of Documents That Support Environmental Qualifica-tion of Licensee's Equipment Attachment 4 Outstanding Items (Licensee Identified) l l i w -~ , - - - - . --, - e v3-w - wve we , ~ , , - - --- .,ysy- * * .n,+ +, w, --
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- 1. . INTRODUCTION .
1.1 General The NRC Office of Inspection and Enforcement (I/E) issued Bulletin 79-DIB, " Environmental Qualification of Class 1E Equipment" in January 1980. This bulletin required the licensee to perform a detailed evaluation 'of ' the environmental qualification on Class 1E electrical equipment required to function under postulated accident conditions s and to submit a report on this action. This document is a report on the evaluation of the licensee's response to this bulletin.
- 2. BACKGROUND AND DISCUSSION
. . 2.1. General The evaluation of the licensee's response was accomplished by per-forming an on-site inspection of selected c] ass 1E equipment and by l examining the licensee's report for completeness and technical accuracy. The licensee's reports used in this evaluation are dated November _1,1980, and therefore, does not include the response to R1
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the bulletin supplement No. 3 which was issued on 10/24/80. ep..-.,- , , . , , - , , , , . , - ~ . , yy,,.,,-.r , . . - ....m,,,,,,,- ,y.,,,,r..,...,..,, ,,rme%... ,-..r.q. ..,,,v..-,,,-,.m._.,,_-, ..-_.u-,%-..-.
*2. 2 On-Site Inspections * ,
The on-site inspection, made on selected lE equipment, verified proper installation of equipment, overall interface integrity, location with respect to flood level for equipment inside the ecutainment, and manu-facturers nameplate data. The manufacturer and model number from the nameplate data was compared to . information given in the Component , E' valuation Work Sheets (CES) of the licensee's report. S Components that were examined during the fiel'd inspection are identi-fied by an asterisk (*) in Attachment 1. If any discrepancies were R1 noted between the installed equipment and the correspondent equipment addressed in the licensee's report, they are discussed in'Section 4 e of this report. The site inspection is documented by report number > 50-270/80-07 of April 4, '1980. 2.3- Evaluation of Licensee's Report , Each component as addressed on the Component Evaluation Work Sheets (CES) of the licensee's report was examined for completeness and ! 1 accuracy to the criteria given in the bulletin. This examination 1
,; I assumed qualification documents (analysis, test reports, etc.) referenced
.. . by the licensee in.their submittal are acceptable.
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i. The ,results of this examination are documented in Attachment 1. The CES page numbers in column 1 of Attachment 1 is the same CES page found in the licensee's report.
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- 3. . GENERAL INFORMATION -
3.1 Identification of Class IE Electrical Equipment The licensee's list of systems was compared to the systems listed on Att'achment 2. 'This list is considered to be a standard list for Babcock and Wilcox, NSSS, PWR reactors. e It is recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, therefore, many of these systems may not exist for Oconee 2 plant or the function of-these systems for the Oconee 2 plant may be performed by comparable systems with different names. In any case, all the systems of Attach-ment 2 were not addressed or listed in the licensee's report. To insure completeness and uniformity of reports of similar design, the licensee has informed RII that Revision 6 to the report, which will be
. . - filed subsequent to Revision 5 (November 1, 1980), will address this matter.
3.2 Service Conditions The service condition accident environment, HELB/LOCA inside contain-
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. . ment and_RELB outs _i,d_e containment are indicated or discussed in the licensee's report and are based on the FSAR accident analysis.
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-3,3 Qualification Documentation Attachment 3 is list'of documents (test reports, analysis, letters, ,
etc.) used bytthe licensee in. determining the environmental qualifica- , - tion . of.' plant ' equipment - for. Oconee 2. These references have been tabulated and are indicated on the applicable CES of their report. ,
- 4. EQUIPMENT DATA REVIEW ;
4.1 ~ Equipment that 'is' considered to meet. IEB; 79-01B requirements are categorized as 1 in the last column of Attachment 1.
., 4.2 Equipment whose qualified life. (Aging) is less than the life of the plant is categorized as' 2 in the last column of Attachment 1.
i l 4.3 The licensee has identified specific equipment which has been or is ' being replaced, modified or relocated as a result of their IEP 79-01B l efforts. This equipment is categorized as 3 in the last column of Attachment 1. 4.4. Equipment whose' qualification is unresolved (such as, a qualification record search is still in process, tests are scheduled to determine qualification, additional information is needed by the NRC reviewer to satis,fy him that equipment is qualified, etc.) is categorized at 4 in
. the isst column of Attachment 1.
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4.5 Equipment that the . licensee has identified as not being qualified required an LER with justification for continued plant operation. No LER's were received in Region II. 4.6 Equipment whose qualification (Aging exempted to a certain degree -
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see DOR guideline Section 4) is unresolved, as identified by the licensee is' list ed in Attachment 4 as Outstanding Items. The licensee has provided justification for continued plant operation for many, if not all, of these outstanding items in their report. In many cases, this is provided on their CES or in a special section of the report. In some cases the licensee states that this justification is by Engineering Analysis that are available at their office. 4.7 On-site inspection data agrees with the licensee's CES information.
,,,- Asterisked items in Attachment I are components examined during R1 the on-site inspection. '
- 5. CONCLUSIONS Dtie to the time constraints imposed by the Commission Memo and Order of 5/23/80 this evaluation is based on the licensee submittal dated
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November 1,' 1980. This licensee's report does not address all items that may be pertinent to Oconee 2 plant as a. result of bulletin supple- R1 ments 2 and 3 issued on 9/30/80 and 10/24/80 respectively. Specifically information on cold shutdown ar_d TMI Lesson Learned related equipment which is received subsequent to 11/1/80 will be evaluated by the EQB of NRR.
The licensee's actions.me,et the requirem'ents of the Commission Memo and Order of 5/23/80 and justification for continued plant operation wh R1 many of the components that have unresolved qualification items is indi-cated in Section 4.6. Based on the information available, the Region II reviewer considers that the justification is commensurate for the areas identified, that the proposed corrective action meets requirements .of ' the Commission Memo and Order of 5/23/80 and, therefore, plant operation R1 can continue untfl these items are resolved as committed to by the licens'ee. This evaluation is based on the on-site inspections, the information supplied by the licensee in their submittal, telephone conversations with the licensee's representatives, their FSAR, and the assumption that the Qualification
., Documents (Test Reports, Analysis, Letter, etc.) are acceptable.
The results of this evaluation does not necessarily impl' ythat the equipment in unreliable, unsafe br represents a significant safety issue; it does dmply that additional information is required. This is indicated by the applicable categorization indicated in the last column of Attachment 1. l i i 4 l t ~ l
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ATTACHMENT 2 FUNCTIONS /SY$TEMS LIST (W) PWR Needed For Mitig'ation Of Consequences Of LOCA Or MSLB
- 1. Reactor Protection
- 2. Safegua,rds Actuation
- 3. Containment Isolation
- 4. Main and Auxiliary Steam ' Isolation
- 5. Main and Auxiliary Feedwater Isolation
- 6. Feedwater Control
- 7. Containment Spray
- 8. Containment Air Purification / Cleanup
- 9. Containment Ventilation / Cooling
- 10. Containment Combustible Gas Control
- 11. High Pressure Injection'
- 12. Low Pressure Injection
- 13. Accumulators -
- 14. Residual Heat Removal
- 15. Chemical and Volume Control
- 16. Pressurizer Spray
- 17. Power Operated Relief Valves 18 *.' Steam Dump
- 19. Containment Radiation / Monitoring
- 20. Containment Radiation / Sampling
- 21. Component Cooling Water
- 22. Service Water
- 23. Emergency Power
- 24. Centainment Sump
- 25. Control Room Habitability 26.- Safety Equipment Area Ventilation
- 27. Aaxiliary Feedwater
- 28. Reactor Coolant i
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, - or W = InJIcates the item is Not Applicable a) Testing schedule but not cocptete , !!L = Indicates the item to Unresolved. Licensee identified b) Reviewer needs additions 1 Information P = Proprietary c) Que s . Record search still in procese , L = Licensee identified 5 - Egulpment not qualifted 1
},
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~ lit. = Indicates tiie itea le Unresolved. Licensee identified 13 ) Reviewer needs additional information
. P
- Proprietary '
c) Emel. kecord aestch still in procese I L = Licensee identified 5 = iguipeent not quellfied I j i R = Reviewer idaptified 6 = lten identified to EQB for resolution , ! = Equipernt is qualified , L I 2 - Aging to less thave lif e of plant with Itcensee bp . indicating periodic replacement /N,,, e DATE /f. d ,, RIVIEWER . i i _ ,
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~ L'L = Indicat=s the ites is tinresolved. Licensee identified r = proprietary b) Reviewer neede additional information L = Licensee identified c) Quel. Record search still in process ,
R = Reviewer identtiged 5 = Equipment not quellised I <l 6a Ites identified to ErlB for resolution
- 1 = Equipment to qualtfled 2 - Ar,ang to less than lite of plant with licensee .
fg Indicating periodte reptocement REVIDiERI / g/ M pf d [/ i - DATE/O/.?[/[6 t j t i t i . I i I..
f -' f ,) *- taiatie I e I OB . SY 5 it *! TER
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!!L = InJicates the item ia !!nresolved. Licensee identified b) Reviewer needs additional inforeustion P = Proprietary
,' c) Qual. Record search still in process
- L = Licensee identified 5 - Equipment not quattfted I i
R = Beviewer ide.ntified 6a Iten identified to Ef]b for resolution 1 = Equipment is qualtfled , 2 = Aging te less than lif e of plant with licensee
- bf Indicating periodic reptarement PEYIDfER ff', J DATE [Y' .M i #
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Page 1. D. *arx t}uJl. Chem. Accur. Sube. Licenare Action outstandin8 Catezor)
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' til = Indicates the item to Unresolved. Licensee identified b) Reviewer needs additional inforswtion Pa Proprietary c) Qual. Record search still in process
- l L
- Licensee identified 5 = Equipment not qualifted I 1
R = Reviewer idepttfied 6 - Itee identified to E/15 for resolution 1 = Equipment is quallffed . i ., t 2 = Aging is less than lif e of plant with licenece
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- - ce N = Indicates the item to Not Applicable I e) Testing schedule best not complete I i
t!L F == Proprietary Intitcetes the item is Unresolved Licensee identified b) Reviewer needs additionet information . i L = Licensee identified c) Quel. Record seertti still in process { 5 - Equipment not quattfled I 3 R = Reviewer idefttfied 6 = lten identified to Eqa for resolution 1 = Equipment to quattfled , l
- 2 = Aging to less andI.atin, than life p.elodIc o,.fcplant r.p ent witle Itcensee
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B = Indtrates the tree to below the flood level 3 = Equipment requires siodification (resolution, ehtelding, etc.) ! V'er s = iniscetes the iten le Settefactory 4 = Quellfication of equipment unresolved , - or N = Indicates the item is I4ot Applicable e) Teottog schedule but not complete + UL = In ficates the Aten to Unresolved. Licensee identifled b) Reviewer neede additional information P = Proprietary c) Quel. Record meerch ett11 in process ,
' L = Licensee identified 5 = Equipment not qualifted I R = Reviewer ideptified 6 = lten identifled to EQB for resolution ta Lyu f pwnt le queltfled -
2 - Aging te less then life of plant with licensee Indicating periodic replacement / ,/ / REVIEWER M N f'A ATE [Lv 2 7_/N I t ' l
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ceae: p ve;; Dyl} 17.1 , B = Ir.11 cates the iten le Lelou the flood level 3 = Lgulpment re<sutres modif f ration (resolution, a.htelding, etc.) *
/or S = trinceter ti.e ites is Satisfactorr 4 = Quattfication of ensutpe.ent unremolved
- or M = !s.Jfcatee ti.e item is t.ot Applicable a) Testing schedule tot not coc.plete Ut. = In stentes the item to Unresolved. Licensee identified r = Praprietary b) Reviewer needs additional information *i' L = Licensee identified c) stual. liecord neatch still in process
- R = keviewer idtptified 5 = tquisment unt quattfled I~ '
!
- L4 ale: ment is qualifted de a lice IJ-ntified to L98 for resolutfore ,
2 = 41ng is less tia.an lite of plant with licens ee / 1:ijtcating perludic reptarement REYIDfER g,f.t.t( ,, / 4 DATE d" /7 [M
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- i a = indicates the item to below the flood level 3=fkulpmentrequiresmodification(resolution, shielding.etc.) ~
V or 5 = Indicates the iteu le Satisfactory 4 = Qualification of equipment unresolved - l
- or N = indicates the item is Not Applicable a) Testing schedule but not complete UL = indicates the iten to Unresolved. Licensee identified b) Reviewer neede additional information P = Proprietary
' c) Qual. Record search still in process L = Licensee identified 5 - Equipment not qualified R = Reviewer identified 6a item identified to EQB for resolution 1 = Equipawnt is qualified 2 = Aging is less than life of plant with licensee f ! Indicating periodic replacement xEVIEWER
- f ftt 'DATE y >
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3 : ! i 8 gag.aLify A! rat:llMtNk I pps - i - fYan Arb 79-018
- SYSTEM i , - , ~ pggg or 7
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- r = Indicates the ites is belc,w the flood level 3 = Equipment requires modification (resolution, shielding. etc.)
{ /or S = Indicates the item is Satisfactory 4 = Qualifications of equipment unresolved
- - or N = Indicates Elie item is Not Applicable a) Testing schedule but put complete j UL = Indicates the itee is Unresolved. Licensee identified b) Reviewer needs additional information j P = Proprietary c) Qual. Record search still in Process l L = Licensee identified 5 - Equipment not qualified i
R = Reviewer identified 6 = lten identified to EQB for resolution f 1 = Equignment is qualified j 2 = Aging is less titan life of plant with licensee ;c Tf 8 ' f .
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! Andir.iting periodic replacement REVIEWER DATE ..-_ i I .
4 ATTACHMENT 2 FUNCTIONS / SYSTEMS LIST
, B&W PWR Needed for Mitigation of Consequences of LOCA or MSLB
- 1. Reactor Protection
- 2. Safeguards Actuation
- 3. Containment Isolation
- 4. Main and Auxiliary Steam Isolation s
-5. Main and Auxiliary Feedwater Isolation
- 6. Eeedwater Control
- 7. Containment Spray
- 8. Containment Air Purification / Cleanup
- 9. Containment Ventilation / Cooling _
- 10. Containment Combustible Gas Control
- 11. High Pressure Injection 12.
. . LowPressureI6(ection
- 13. Accumulators
- 14. Residual Heat Removal
- 15. Chemical and Volux.e Control
- 16. Pressurizer Spray
- 17. Power Operated Relief Valves I
. . . 18. Steam Dump. _
- 19. ' Containment Radiation / Monitor
~
20.' Containment Radiation / Sampling
Attachment 2 Page 2 of-2
- 21. Component Cooling Water
- 22. Service Water
- 23. Emergency Power
- 24. Containment Sump
- 25. Control Room Habitability
- 26. Safe'ty Equipment Area Ventilation
- 27. Auxiliary Feedwater s
- 28. Reactor Coolant e
4# 9 ee es , 9 e
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- I Documentation References .
. 1
\
fr %. FSAR Ch. 14, Fig. 14-63 (Temp. In Containment) i ! . FSAR Ch. 14. Fig. 14-59 (Pressure in Containment) l
.'l -
MDS Report 05-73.2, Fig. 2 3-3 (Temp. In Penetration Room) MDS Report 05-73.2, Fig. 2.3-2 (Pressure in Penetration Room)
~ $. FSAR Sup. 6, Q15: Sup. 7, Q4 - Res. of 8/11 and 8/28/70 (Chemical Spray)
I 6. Limitorque Test Report 600198 and FIRL Test Report F-C3441
,' l 7 Rotork Test. No. N/ll/4-1970
%,. Okonite Engineering Report Il0E I
3 Okoni te Eng'ineering Repor t s lial and N-1 10; Doston Insulated Wire Test Report B901
- t. 11 12[.Franklin Report F-C4350-3 and Anaconda Letter dated 6/1/79 Raychem Spec. 44 dpted 4/12/68, Cabl.c Data Sheet dated 3/30/67, Military Spec. MIL-W-81044B, Duke Power Company Stock File 1-D-1 13, Franklin Report F-C2750 14'. Duke Power Company Report No. TR-012 15 B & W Report No. 58-0081-00 ,
161 ' Joy Manufacturing Test Report X-604 !
- 17. B & W Report No. 58-0080-00 t
'; 18, Penetration Qualification Reports
.s 19. B & W Test Report 58-0093-00
- 20. B & W Test Report 58-0261-00 and 58-0220-00
- 21. Limitorque Test Report B0003 '
l
- 22. Franklin Test Report F-C3271
- 23. Duke Power Company Post-Accident Radiation Analysis Study 24' Let ter f rom C. A. 0 riggers to R.
F. Wardell dated 3/25/80 25 Limitorque Test Report 600456
- 26) ) Westinghouse WCAP7829
.. 27i - Wes t inghouse WC AP8754 -
2S 29,} Wyle Lab TestFranklin 17374-1 Report F-C4113 and Brand Rex Aging Test
- 30. Okonite Engineering Report 31; Duke letter (Steam File 05-815-0%) dated 7/15/80 32' .
Louis Allis letter dated 5/30/80 and Radiation Qc lification Sheet 33j B & W Topical Report No. BAV-10003A, Rev. 4 Franklin Report F-C3683 34l
, 4 d
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OCONEE 2 ATTACHMENT 4 - NOTES l l
- 1. Item to be replaced; licensee identified desposition schedule is identified i on specific CES.
- 2. Testing scheduled but not complete, or qualification record search is still in progress; licensee identified.
3, .st- J. E t n f t o bss sfah al ir.
- 5' I' "M N AU N d'd 5I'*S hv.e n ow hm or ,1 3 <d + b f- %7 n ilI hof 6< rJr < t d Thw CODES: U'J m1 s v./ pts Nn C E f, w :)the yt yrsj ,1 sh Uir & b. RJipmu, CASS -
Chemical Addition and Sampling System CSQT - Containment Spray Quench Tank ES - Engineered Safeguards HPI - High Pressufe Injection LPI - Low Pressure Injectica MS - Main Steam - RBV - Reactor Building Ventilation CCS - Component Cooling System FDW - Feedwater ^ LPSV - Low Pressure Service Water LWDS - Liquid Waste Disposal System RBS - Reactor Building Spray - RC - Reactor Coolant RPS - Reactor Protection Systen PT - Pressure Transmitter CBL - Cable SV - Solenoid Valve Ta - Terminal Board XZOR6 - Transzorb 's
- PS - Pressure Switch LT -
Level Transmitter MOV - Motor Operated Valve I 1
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