ML20235U045
| ML20235U045 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/07/1987 |
| From: | Russell J TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710130334 | |
| Download: ML20235U045 (52) | |
Text
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..p j TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant-P. O. Box 800 1 Spring City, Tennessee 37381 October 7, 1987 U.S. Nuclear Regulatory Commisrion Attn: Document Control Desk Washington, DC 20555 Gentlemen:
In the Matter of the Application of )- Docket Nos. 50-327, 50-328 Tennessee Valley Authority EMPLOYEE CONCERNS TASK GROUP (ECTG) -NRC RAI ON SEQUOYAH ELEMENT REPORTS 235.08 AND 241.02 The following is our. additional response on the subject elements requested by-the NRC'in a telecon on September 22, 1987.
Employee Concern Report 241.2(B) Revision 2 Reguest: Provide scope and status of corrective action on the PIDG terminal'
. lugs for solenoid valve arc suppression networks (Para 10.2 and 10.3 in subject report).
Response: a. Engineering report ER R1 SCR.SQNEEB86201 R0 Attachment 1 identifies the rework scope of PIDG. terminal lugs on arc suppression networks on safety-related solenoid valves (Enclosure 1).
- b. Work requests initiated by construction' provide specific instruction to' inspect and replace terminal lugs if not correct on the suppression networks for solenoid valves.- For a typical work request, see enclosure 2.
- c. The corrective action for unit 2 has been completed. . The verification has been performed by Bechtel, consisting of reviewing the documentation described in (a) and (b) above and l performing a visual inspection of randomly selected solenoid )
valve are suppression networks listed in (a) above. The verification is documented in enclosure 3.
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8710130334 871007 PDR ADOCK 05000327
!nk ipl ,
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1 i An Equal Opporturiity Employer C _ ___ _ J
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U.S. Nuclear Regulatory Commission !
Employee Concern Report 235.8(B) Revision 1 Request: Does the Central Laboratory qualification test include the energy contribution resulting from superheated steam during the steam line break accident?
Response: a. The TVA Central Laboratory qualification test (C186-86-1155) does not include the energy contribution resulting from steam during a main steam line break (MSLB) in a main steam valve room (MSVR). PVC jacket integrity will not be maintained I during an MSLB; therefore, no pressure differential will exist j between the inside and outside of the flexible conduit. The evaluation for submergence is based on the assumption that the i drains in the MSVR are clogged. In addition, there is no beta ;
radiation to shield from. For environmental data, see drawing I 47E235-79 R4.
- b. The TVA Central Laboratory qualification test does not completely include the energy contribution resulting from steam during the most severe steam line break (HELB) in the containment. The test only envelopes the temperature profile j
for the first two hours of an HELB. The pressure was not j recorded. For environmental data, see drawings 47E235-44 and
-45, R3.
To demonstrate that the PVC jacket of the flexible conduit used inside the containment will not flake off and/or melt off and clog the floor drains when exposed to the HELB or Loss of Coolant Accident (LOCA) conditions, a search for applicable test data was performed. No test data were available that specifically addressed the PVC jacket on flexible conduits.
l However, test data are available on PVC-jacketed cables. The test was performed by Wyle Laboratories for cables used at Browns Ferry Nuclear Plant (Report No. 17513-1). The test provides data which can be compared to the PVC jacket on flexible conduit. The cables were temperature and radiation aged to simulate a 40-year life, followed by exposure to HELB/LOCA conditions including pressure. The environmental parameters used in the test are compatible with the parameters l established on Sequoyah. The conclusion is that the PVC jacket l on the flexible conduit will not flake off and/or melt off, and, therefore, will not clog the floor drains.
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p't t 3 i; l U.S. Nuclear Regulatory Commission l l
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The maximum containment pressure excursion of 25.8 PSIA as a 1 result of a LOCA will not have any impact on the-integrity of
~~
i JJ the PVC-jacketed flexible conduit for the following reasons:
The conduits have generally been sealed for.a differential-l' pressure of six inches of water (approximately 0.25 PSI);.
therefore, the differential pressure of.approximately 12 PSI will break the conduit seals and equalize the pressure inside and outside the flexible conduits.
- The flexible conduit used on Sequoyah is made'of steel and has sufficient strength to withstand an initial differential pressure of 12 PSI. ]
Please contact Ron Gagne.(615) 365-3788,, Watts Bar, if you need further assistance.-
Very truly yours, TENNESSEE VALLEY AUTHORITY l
-B 1 ames R. Russell- ]
Watts Bar Nuclear Plant ECTG Licensing Manager cc (See page 4.):
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4 U.S. Nuclear Regulatory Commissien i
cc (Enclosures)
Mr. G. G. Zech, Assistant Director l Regional Inspections Division of TVA Projects Office of Special Projects ,
U.S. Nuclear Regulatory Commission i Region II l 101 Marietta Street, NW, Suite 2900 !
Atlanta, Georgia 30323 j i
Mr. John A. Zwolinski, Assistant Director For Projects Division of TVA Projects i Office of Special Projects i U.S. Nuclear Regulatory Commission I 4350 East West Highway !
EWW 322 I Bethesda, Maryland 20018 l
Sequoyah Resident Inspector {
Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 l
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- 1. C1 Calculatisc entitled Duty Cycles For Specificed Seleneid Yelves" SQR-0567-0036 (125 860730 800) 4 4
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S.e fc11 vitt le a list ef all Class 13. DC, o;1enoid valver, with are I sw;preselos netw:rks which need to be energised to perf ors' their saf etF function: - (
1 - F57- 1 -6 8 3
~1-Pst'-1-133 ' 2-F8Y-1-68s- -
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l 1-F17.-1-248 2-FST-1-248 i-"S 1-psv-1-313' 2- psy-1 -318 - " l
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2-LST-3-1 $6 1-LST-3-164 2-LST-3-1646 i 1-LSV-3-164A . 2-L57-3-164A 1-L87-3-171 2-L57-3-171 L$Y-3-171A ..
2-LSV-3-171A
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1-L57;3-! ?S , IW 2'-LC7-3-174; l'12 1-Lsv-3-175 28'73
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SEQUOYAH EARS)I D7110NMDi7 C1. ASS 1 E $0LD0!D TALVES WHICM NEED 70 tt DEAC12ED TO FZ3J01.M TELIA SATETY RfNCTION l
2-FSV-6 5-4 $ 61 S . *
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IEQUDYAH MILD ENV!A0NMENT CLASS 1E SOLENOID VALVES WHICH NEED 70 BE EbERGIZED 70 PEEFORM THEIR SAFETY FUNOTION 1-PSV-46-9A 2-Ts7 46 9A 'C4*0 1-F37-46-95 -
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' CLASS 1E 125YDC 1
DC CONTACT INDUCTITE LOAD STUDY 1 I
1.
For conservatics, relay and solenoid valve lead 2.
maximum systaa voltage of 140VDC ratherothan tate.
nominal v ls w
- Data contained herein was obtained from the following sources:
a.
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EQ bladers (20CTR$0.49 list) \
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- b. lists (SQE1.) inside and outside contain Wiring circuita diagrams associated with 125V vitalery batt A board III \
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MAINTEN ANCS RECUEST FORM-TVA NUCLEAR PLANT EQUIPM D ENTI-F IE R: DATE: poNTW OAV W E A 8, l l EQUIPMENT NAMES
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W THIS COMPONENT AND/OR $USCOMPONENhS) MAS BEEN INSTALLED kM { AT THE FOLLOWING UNID LOCAfl0N: O O Z p ,,,{ ,4 l 8 nDMN C U:$Y ' _ MFG. CCOEINAMEl N - I -1 MFC. SERIAL No. l l l Y///! { j l j j l } l l l l l l ..- TllC No. g WG. MODEL No. l l l l l h l.l l l l l l l l l l j j l ii" " QUAuFiED UFE-(( { % ]Y w wG CODE /Nr.ME[ [ l\g ggp ITEu INSTALLED: .4# g wG.sEalit h.. [ p l .4 - l _ l l l ; ; j l l tl l] g inC N.. a
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I ADDITIONAL REMARKS: Coordinate all work through Operations. . Document all ennfleurne 4 s a{ changes per MI-6.20. Perform inspection on Surre Suppression Network located in 4.me* ten box 2 d '/'7 . This is a 10CFR50.49 device and must be inspected for mountine bote integrity, rust, missing cover screws, standing water in bottom of box, and debris coverinal weepholes, if applicable. The terminal blocks are also 10CFR50.49 and must be inseneend for cleanliness and corrosion. If terminal blocks are coated, recoat with Dow Cornina RTV 3140 if disturbed. Inspect Suppression Network for the use of_ insulated ring centue ji connectors on the_ solid leads of the diode or resistor. No ring tonaue lugs are to be cut off on any components. ] If this situation is found on either comnonent. re=nva comennowi and identify for future testing. Replace any component removpd usinz Amo Solistrand rinr tongue lugs (uninsulated). Before replacing diode, insure that the factory markings
.,-- e, ;, . u , v..
(Annode and Cathode) are not reversed. Verify the new diode'is installed sopropriatelv i (polarity wise). Were components replaced / yes l no, if yes list on back of I MR form. All terminations are to be made per M6AI-7,(TC > 9 -00~7QA required). - PMT is required if \ components are replaced or wires lifted. If no work is performed, the PMT may be waivered. After maintenance is completed, insure junction box cover is secure. [ u j. fy ,,..,. lll.kudlltS(51 , ,\
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Revision 10 ' wn/a no. 41/#44 ' Step 3.2 Unit operator '; F
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Retorque electrical connections as required by MEAI-9. \ i Step 4.4 , SE/SNO and UO notified of week performed on this data sheet l Notified By,h/Mpf9A) ffff ////flA7 Signature i Date Verification must be performed by individuals qualified in accordance with AI-37. 0287M/1sh
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l SQtt MI-6.20 - ';I Page 3 I Revision 10 i DATA PACKAGE COVER SHEET I. To be completed by the originator of the work data package. List the equipment tothat documents are required to perform the work and return the service. 1. NR/MR' number (s): MJ/[4 74 l 2. MI data sheet number (s): /7/f- 4.f4 , J, y5 4 .*d7g r'._ A7+7 f ' ""' ' S W 7 1
- 3. I "7~ /4 L 4, SI data sheet number (s) M f/ rd /8s/f_d fMf]
4. Material certification requirements: [4 M 5. Other documents: /#f(M2'-7' 7( p 7 -O C "7 ._^ _')c. dry 4 f9 Yfr - All required documenti 4 on is in the data work package.
=w ones Originator 97 iiork a Package
! /~/.2*P7 Date j II. Results review and appro al f the above data package (attached). i M D- / ~l ~ $ 9 'S ~7 Responsible Maintenance Representative '
Date - i _. ,, ~ Maintenance Supervisor W s- ty l @ ~'81
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. , ;t~l Bechtel Western Power Company.
Ewaineers - Construe: ors Fifty Beale Street San Francisco, California Med Adewees: PO Bos 3965. San Francaca CA 94119 September 16, 1987 BLT-483 Mr. George R. McNutt J Engineering CEG-H Tennessee Valley Authority Knoxville, Tennessee 37902
Subject:
Watt s Bar Nuclear Plant Employee Concerns Evaluation Program Tennessee Valley Authority ' Job No. 16985-026 CATDs 241 02 SON 01 and 02
Dear Mr. McNutt:
In accordance with ECTG procedure ECTG C.3, Revision 5, attached is the "ECTG Verification Closecut Checklist" for the subject CATDs. l Very ly yours, , i G. .P kinson l Po- Manager I
%.0 Y GLP/AR/df/3681D l Attachment (s) c
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*4, ,
ECTG C.3 . Attacnment E .N Page 1 of 2 - Revision 4 ECTG VERIFICATION CLOSE0VT CHECKLIST CATD No. 241 02 SON 01 & 02 This CATO was designated: C/A completion notification Memorandum RIMS No. 503870708850 __ M QR CAQ No. SCRSONEEB86201 This memorandum denoted CATO: []NOR Partial Closure M Complete Closure For Unit 2 only*
SUMMARY
- C/A clements reviewed M Walkdown documents M Procedure and/or drawing revision
$Documentand/ordrawingreviews ;;Trainingrecords tJ Examination or test results .. Modification (ECN) documents i
[] Engineering analysis ,, New program (s) [] Repair or replacement records .. Other - specify i DISCUSSION: In TCCA-02, dated 07/30/87, TVA indicated that the corrective actions for CATOs 241 02 SQN 01 and 02 were completed and that the evaluation team could proceed with the completion of verification of the restart i corrective action. Accordingly, the evaluation team performed several walkdowns starting 08/03/87 to determine the adequacy of the corrective actions implemented. The evaluation team followed up with a letter (BLT-477), dated September 09, 1987, to indicate the outstanding items. This verification is for unit 2 only; unit 1 has nat been verified by the evaluation team since the work is in progress. l l PJContinued - i i
Conclusions:
Corrective actions were adequate M Yes [] No []N/A Yes No N/A M [] []Deficienciesadequatelyscoped " N []Deficienciescorrected ; M []Actionsrequiredtopreve,n recurrence co lete l M 2 u
' / Signature y 9- /(-67 Date l
1 36700-R2
)
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- t ECTG C.3 Attachment E .&.
Page 2 of 2 Revision 4 ~ ECTG VERIFICATION CLOSE0VT CHECXLIST CA N O. 241 o2.SQN cl302. Initials Mko Date f-M-87 DISCUSSION: (Continued) TVA has completed the two outstanding items indicated in the letter. The evaluation team has verified through the walkdowns and through the documentation presented by TVA that the work indicated in the corrective action plan has been completed satisfactorily. Conclusion The evaluation team concurs'that the corrective action plans have been adeauately implemented. This closes the issue of the improper use of i PIDG terminal on solid conductors. fav. w t 3.. References a. Walkdown performed by S. Mabie, Bechtel (IOM 1827),(08/25/87) b. Walkdown performed by S. Mabie, Bechtel (IOM 1828),(09/10/87) c. Walkdown performed by S. Mabie, Bechtel (IOM 1829),(09/08/87) d. \ WalkdownperformedbyS.Mabie,Bechtel(IOM 1830),(08/28/87)
- e. .
Walkdown performed by S. Mabie, Bechtei (IOM.1831), (08/27/87) f. Walkdown performed by S. Mabie, Bechtel (IOM 1832),(08/27/87) c. Walkdown performed by S. Mabie, Bechtel (IOM 1833),(08/26/87) h. Walkdown performed by S. Mabie, Bechtel (IOM 1834),(08/10/87) . i i. Walkdown performed by S. Mabie, Bechtel (IOM 1835),(08/26/87) j. i Walkdown performed by S. Mabie, 8echtel (IOM 1836),(08/25/87) k. l.etter from electrical maintenance personnel regarding cable termination,(IOM 1837)(10/07/85)
^
1. Walkdown performed by S. Mabie, Bechtel (IOM 1838),(08/25/87) []Discussioncontinued 16700-R2 l
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