ML19296D158
| ML19296D158 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/22/1980 |
| From: | JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19296D157 | List: |
| References | |
| IEB-79-14, NUDOCS 8002290418 | |
| Download: ML19296D158 (12) | |
Text
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- 1 pescIn CF r.;3:-LCT!O;; Cci;;UC"J.D AT CYSTLECFECKl~CLCEGiiiEElTI'IUII=[II ,
- ACCCRLMrt i;IW IL JL~l LTU 79-1#' " # * *,
(Ild;CCESSIBLE PCRT:C';2 CF SAFcz' FIU\TED SYSTC4S) 8002290$5,
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Tnis incpectica was initistcd in accordance witn tne recuirements of In cection cnd Enforccmcnt Eulletin 79-14 and 79-14, hev. I d:ted July 2,1979
- nd July 18, 1979, rcspectively, entided "Scismic Analysis for As-Euilt safety Felated Piping Systems." inis bulle:in recuested specific cctions to be perfccmed by the licensee and reportcd to tne SFC Cf fice of Inspection an3 Lnfcreement. J:FOL recconac<J to Item 1 cf tne rulletin by letter dsted August 1, 1970, in wnten a commitment was m ic :c ocrform tna incocction referred to in Itcm 2 of tnc balletin. Ey letter d tcd August 21, I??9, JCML recpondcd c Itr 2 cf t.;c tallctir., s.nicn include; c rcpcr (::t:cncd :s '>cpcndix li cf tne ir. cecticr. cf normally :cccssibic pcrtion cf 3 fety rel :s_d piping.
Inis report cro.15es tne rc:alts cf tn2 inct;ection cf normally inc.ccercicle cernen: :,f cd j r ;1ctca p;pirr:, ;a referred to in : tem ? cf tne colletin. 's actcd in :ne ,ugust 1, 1975 1;t:ct, tne Cfster Crces plant was licensed prior to tn: incuence of celamic c:tegory 1 recuirements; tacrcfort, tac inc?cction .s:: pcrformcd to 'ecrify tan t:4 c.ctunl configurc:icn of acfety rcl:t.~J systcms, utill:1ng picing 2 1/2 incne: in di. meter :.nd greater, meets design rccuirements. T:.e inspection wac, no.iever, expandcd to includc
-dditional systcms inside contain.mcnt cnd tne rtccective results are included.
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Tne systems which were insoccted are these listed in Table 1 where the piping dicmater was 2 1/2 inches or greater. The inspection consisted of compcring the as-fcund condition of piping, vcives, supports, and restrcints witn the design docu cnts used at input to the seismic analysis. Pnase 1 cf tne program w:s accomplished by engineers whc physically inspected the ystems noting any devictions from the design deceents.
Pn:sc 2 cf the inspection ccnsisted of rcvicuing the re:ults of En:ce 1
- .nd svcluating any Javiaticns tc cetermine whet.nar cr not c nonconfermance entst:C. C2viction: acre nct ccastCcred ncn-conferm:necs if enc installstien n:5 ccan ; cr ifiW to cccc=cdate ccrual cor,diticns in tne field :s long as t:.e aviction did not prevent the installction frc" performing its intended fer:ction. Personnel wnc cre spccialists in tnc fielo of pipire strecs cnolysis snd nanger design =ac en en:inecring judgment ss to anctner cr not tn? cxisting ccnfigur:ticn fulfilled tnc design cbjcctives. .;cncenfermances were identified in tnose instances encre:
- 1. 3e piping gt-cmetry diffcrcd significantly frca
- design docu cnts; cr
- 2. Actual valve positions and weignts differed significantly frcm design dcctrnents; or
- 3. Tne enginecring evaluation concluded that the existing configureticn may not fulfill the design requirements; or
- 4. The installed hanger was a different type than specified in the design dcct:nents (i.e. rigid instead of spring, etc.); cr
- 5. 'Ite instclled hanger was found to be damaged; or
- 6. fne installed hanger was fourd to be incperable; or
- 7. 'ihe installed location of the hanger was found to be more tnan 2 feet frcc tne location specified in
'3e design documents; cr
- 3. The design documents irdicated a hanger wnere none existed; or
- 9. A hanger was installed wnich was not specified in the design document.
Pnase 3 of the inspecticn consisted of cither par ?rning an cnalysis to verify that the nonconformance did not affect system operr.ility or restoring the existing installation to conform to the design specifications.
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- 10. CILEC .1:CY 3C.F.VICT., .ATER
- 11. CCl:TPCL PCC CF.IVF
SUy/GEY Cf tne systcmc listed in Table 1, ro nonconformances were identified for tne feedwater, Eecirculation, Core Spray, er Control Pod Crive Systems. Cf tne 309 normally incccessible items enat. were inspected, 29 ncncenformances were identific5. Tne nonconformances were evolucted and, except for tnose items listd below, were found to fulfill design recuirements. A 110 ting by system of
- 11 nonconformances identified is provided in the following dats sheets.
Pepairs or mMifications indic:ted in tne resolutien of nonconfor .:nccc will be cc pleted by tne end of the 19E0 refueling outage; ct wnich time :11 items in:cected will sect tac design recuirements used as input to tne seismic
- n:1ysi: cf calcty rel:ted cystcms.
The first itcm tr.st u:s evclutted s not meeting design require'.cnt ccnccrn tm tacrgenci Can'. nscr Jytt:T. U, con rcnovcl of tne insul? tion cf c ncrgency Cenacnser pioing it war discovered tnat 9 anubber pipe c1cmps were impre g rly installed. Inis situaticn v.cs ev:1uatcd and it u:c determined thct cyctcm oper:tien mignt aave been joc,:ardi:M.
Tne cecond itcm that w:s cv lutted as not meeting design requirements concernc tne Liculd Poison system. The inspcction of this system revealed that thres of the pipe cl: ps were not properly 1ccated in tncir restrcint boxes.
Inis cituation wcs evaluated cal it was determined tact system cper: tion mignt hrve ceen jeopardized.
Tne tnird item that wac ev:luated as not meeting decign requirements concerns the Cleanup Dcminer lizcr Systcm. The inspection revealed that snubber CC-1-R2 accounted for loads in one direction only. Tne design documentation indicated tnat twc directional support in required at this point. This situation vac evaluated :nd it was determined tnet cystem opcr tion might have been jeocardiced.
Pursuant to cur Technical Specificcticas, Ecportable Cccurrene" Feport numbets 50-219/80/3-1P cnd 50-219/80/10-IP were sent to the NEC Region I Of fice of Inspection and Enforcement. A copy cf the Reportable Cccurrences are pres.ented in Appendix 2.
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- System: MAIN STEAM --
Hanger Mark Nonconformance Remarks / Resolution No.
MSH-4 A Hanger not installed as per Does not affect system design design documents. requirements.
M3H-4B Hanger not installed as per Does not affect system design design documents, requirements.
MSH-8A Hanger not installed as per Does not affect system design design documents, requirements.
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FGH-8B Hanger not installed as per Does not affect system design design documents. requirem en ts.
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System: CONTAINMENT SPRAY Hanger hbrk Nonconformance Remarks / Resolution No.
227-R2 Snubber replaced by X-63-SS-2 Does not affect system design support. requirements.
6dditional Two additional partial restraints Does not affect system design
<estraints not indicated on design documents, requirements.
are located on the southeast header feed line. _
- Piping Lower outer header en west side Does not affect system design l Geometry is indicated as 17.S' on design requirements.
l documents. Actual dimension ir
! 26',
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I NQ-2-H2O Hanger not installed as per design Does not affect system design i documents. requirements.
I
System: SHUTDOWN COOLING Hanger Nonconformance Remarks / Resolution lNo.
Mark 556-R1 Restraint not located as per Does not affect system design design documentation. requirements.
556-R2 Restraint not located as per Does not affect system design design documentation. requirements.
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System: POISON Ranger Mark Nonconformance Remarks / Resolution No.
NP-2-RSA Pipe clamp not found in restraint Reinstalled pipe clamp to proper box. Position.
NP-2-RSB Pipe clamp not found in restraint Reins- 'ed pipe clamp to proper box. positicn.
NP-2-R9 Dipe clamp not found in restraint Reinstalled pipe clamp to proper box. position.
I iNP-2--R8C l Additional restraint not indicated Does not affect system design ion design documents. requirements. 4 l
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Additiond Additional restraint not indicated Does not affect system design Restraint on design documents. requirements. ,
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Piping Piping geometry near penetration An additional spring hanger, NP l Geometryto vessel does not agree with H1A, will be installed. Does not design documents. affect system design requirements.
I
System: CLEANUP Hanger Mark No.
Nonconformance Remarks / Resolution ND-1-R2 Design documentation indicates An additional snubber will be two directional support. As- installed, built supports in only one direction.
I
' Piping Piping geometry does not conform Does not affect system design
! Geometry to design near penetration. requirements.
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System: EMERGENCY CONDENSER - OUTSIDE CONTAINYc.NT Mangcr Mark Nonconformance Remarks / Resolution No.
632-R1 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage.
632-R2 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling cutage.
~
632-R3 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage.
I 632-R4 Not attached to piping as Will repair as per design before end
! indicated in design documents. of 1980 refueling outage.
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!632-R7 ' Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage. l, r
! l l633-R1 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage.
633-R2 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage.
633-R3 Not attached to piping as Will repair as per design before end indicated in design documents, of 1980 refueling outage.
633-R4 Not attached to piping as Will repair as per design before end indicated in design documents. of 1980 refueling outage.
System: EMERGENCY SERVICE WATER Hanger Mark go, Nonconformance Remarks / Resolution SW-2-H1 Hanger not installed as per Does not affect system design design documents, requirements, SW-SN-30A Additional hanger installed not Does not affect system d ign I indicated on design documentation. requirements.
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AFPCDI'A 1 '
, , .. , , Jersey Central Power & Ught Company 3.w!(,i*.[.M uxh. s
/ f p "j Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 August 31, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
Subject:
Oyster Creek Nuclear Generating Station i;ocket No. 50-219 IE Bulletin 79-14 and 79-14, Rev. 1 By letter dated August 1, 1979, we responded to IE Bulletin 79-14, Rev. 1 entitled " Seismic Analysis for As-Built Safety Related Piping." In this response we indicated that an inspection in accordance with the IE Bulletin had been initiated and a report of the results of this inspection would be submitted by September 1,1979.
Attached is a report of the inspection conducted at the Oyster Creek Nuclear Generating Station. Of the 295 items inspected, thirty-four nonconformances were identified. Each nonconformance was evaluated to determine the effect on design requirements. In most cases the non-conformances did not affect the system design requirements; however, nonconformances were identified affecting the operability of core spray system II. Consequently, Reportable Occurrence Report No. S0-219/79-27-IT was submitted to the Office of Inspection and Enforcement pursuant to our Technical Specifications. This situation has since been corrected and core spray system II is now in conformance with the system design requirements.
Of the total number of inspection items, only 34 nonconformances were identified, and of these, only 6 were found te, affect system operability.
Since, with very few exceptions, all nonconformances have been corrected and/or found not to affect system design requirements and since the number' of nonconformances were a small percentage of the total number of inspection items, it is felt that those systems which are inaccessoble will likewise prove to be installed in accordance with design documents. Even though core spray system II was found to be inoperable (considering seismic loads), this situation occurred in a test line as a result of local phenomenon and it is not expected that this situation exists in the inaccessable portions of this or any other system.
The next scheduled shutdown of the Oyster Creek p1pnt will occur January 5,1980; therefore based on the above discussion we request Cb
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that submittal of the report required by item 3 of IE Bulletin 79-14, Rev. 1 be delayed until February 22, 1980. We feel that this delay will not adversely affect the health and safety of the public based on the results of this inspection and the relatively short duration of operation allowed by the delay.
Vr truly yours, lD. A. Ross -
Manager-Nuclear Generating Stations la ec: Director Office of Inspection and Enforcement Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
REPORT OF INSPECTION CONDUCTED AT OYSTER CREEK NUCLEAR GENERATING STATION IN ACCORDANCE WITH IE BULLETIN 79-14 (ACCESSABLE FORTIONS OF SAFETY RELATED SYSTEMS)
DUPLICATE DOCUMENT Entire document previously entered into system under:
ANO ,!
No. of pages:
9 4
0 APPENDIX 1
. /'
SCHEDULE FOR ANALYSIS / MODIFICATION ITEM SYSTEM COMPLETION DATE NE-1-H7 Isolation Condenser Analysis complete by October 1, 1979 Penetration Snubbers Isolation Condenser Review complete by October 1, 1979 SW-SN-3 6
SW-SN-4 Emergency Service Modifications complete -
Kater by September IS, 1979
9 APPENDIX 2 ,
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. Jer::ey Ccatt-l Pevict L U-ht Cornpeny
," ~l l 2,l f.'stscn k en.e a: Fun: . Le.1 Read f.'.ctr::.:cen. Ne.. Jaetay 0-d3 (201)455-8200 August 21, 1979 lir. Boyce H. Grier, Director Office of Inspection and Enforcement Region 1 '
United States !!uclear Regulatory Cc=nission 631 Park Avenue Ki.g*of Prussia, Pennsylvania 19406 Cear Mr. Grier:
Subject:
Dyster Creek Nuclear Generating Station Docket flo. 50-219 Licensee Event Report Reoortable Occurrence No. 50-21o/79-27-1T This letter forwards three copies of a Licensee Event Report to
. report Reportable Occurrence No. 50-219/79-27-lT in compliance with paragraph 6.6.1.a of the Technical Specifications.
Very truly yours, jm ~-
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Donald A. Ross, Manager Generating Stations-Nuclear pk Enclosures [
cc: Mr. John G. Davis, Acting Director (40 copies) N Office of Inspection and Enforcement ( U United States Huclear Regulatory Corenission Washington, DC 20555 Mr. Villiam G. Mcdonald, Director (3 copies)
Office of Management Infortnation and Program Control f, United States !!uclear Regulatory Cor nission g Washington, DC 20555 /gU
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mr,.c . .c . A::: FRcs stE coNSECt:E::CES On August 7,1979, during an inspection of seismic restraints associated l with Core S;: ray System II, four seismic restraints, NZ-2-R3,liZ-2-R7, , NZ-2-R8, and NZ-2-R9, were discovered in positions other than required by y original design or had failed. On August 8, 1979 two core restraints, ; M2-2 7.6 and !:Z-2-R6A, were fcund to be in a condition not representative I of :he origiral design criteria. Core Spray System 11 -as considered ; ir.ocerable for a time until analyses were made and condi tions corrected. ; 6:o s : t. :ust A.ss ec . =. vttvs
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..u (201) 455-6734
OYSTER CREEK NUCLEAR GENERATING STATICS Forked River, Ne.-e Jersey 03731 Licensee Event Report - F.eportable Occurrence No. 50-219/79-27-iT Re:crt Date Au ust 21, 1979 Occurrence Date August 07, 1979 I c"! *#iCation Of Occurrence Discovery of six seismic restraints for the 6-inch core spray test lire, which viere either in positions other than required by original design criteria or had failed. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a.9 Ccnditiens Prior to Occurrence The plant was operating at steady-state power. Power: Core 1909.16 Mwt Electric 639 Mwe Flow: Recirculating 15.2 x 104 gpm Feedwater 7.143 x los Ib/hr Stack Gas Ac'.ivity: 27,900 uci/sec Descriotion of Occurrence On Tuesday, August 7,1979, during an inspection of seismic restraints associated with Core Spray System II, it was determined that two seismic restraint (NZ-2-R5 and R9) clamps were not in their as-built position. Additionally, one restraint, NZ-2-R7, was found to have its wall attachment bolts sheared, rendering this restraint inoperable. The structural configuration of the fourth restraint, NZ-2-RS, was found to have been altered. All of the restraints are connected to the 6-inch test line for Core Spray System II. Because of the configuration and condition of four restraints, System 11 was considered inoperable at this tir.e until further analyses could be performed. l After returning the above four restraints to their as-designed status on August 8, 1979, two more restraints, NZ-2-R6 and R6A, were found to be in a condition r.ct representative of original design criteria. The condition of these t.to restrair.ts alone did not justify declaring System 11 inoperable at tnis tir.e. i
r.; .- .c. : v. . . . e u . s u e ..w. av ~.oos -. . .- A'b.s.Z' I?!? A: :r-:-t Cause of Occurrence F ur of the seismic restraints, NZ-2-RS, R6, R6A, and R9, were found to be installed contrary to original design criteria. Because of the failure to install the above restraints properly, restraints NZ-2-R7 and NZ-2-R8 were danaced due to unrestrained pipe movement in other sections of the piping. Analysis of Occurrence The 6-inch test piping routes water in the core sp.ay r system from the , discharge of the core spray booster pumps through a notor cperated test isolitica valve located close to the core spray line, a check valve located in the area of the torus and into the torus. Failure of the restraints during a seismic event could have produced a failure of the test line at some point between the motor operated test isolation valve and the check valve. The significance of this event is that core spray system function would not have been impaired by the failure. Primary containment - would be maintained by the reliance on a single check valve. The check is not part of the local leak rate testing program since normally it does not serve as a primary containment isolation barrier. Therefore, the integrity of this valve is not known. Corrective Action All restraints were restored to their designed condition with the exception of restraint NZ-2-R7 and NZ-2-R6. NZ-2-R7 design was modified to provide easier placement of anchor bol ts. Core Spray System I was on an accelerated surveillance test schedule until System 11 was declared operable. NZ-2-R6 will be restored to original design or relocated based on radiation levels in the reactor cleanup filter sludge tank room. Fallure Data Piping restraints designed by: Bergen Patterson Pipe Support Company Clifton, NJ
APPEhTIX 3 s
Updating of As-Built Drawings Recently, responsibility for the control and updating of as-built drawings has been transferred to the Generation Engineering Department. Procedures are being developed to assure that As-Built drawings are updated to reflect modifications of piping systems in a timely manner. Existing procedures require that these drawings be revised as.part of the engineering effort; however, it is expected that the new organization and revised procedures will provide greater control of these drawings. The results of this inspection will be incorporated into as-built documents on an expedited basis. Burns 6 Roe has been contracted to provide As-Built Drawings reflecting the information learned as a result of this inspection. _
e' e 7 m APPflDIX 2
4 T0: Boyce H. Grier Directorate of Regulatory Operations-Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 FRCM: Jersey Central Power & Light Company Oyster Creek Nuclear Generating Station Docket No. 50-219 Forked River, New Jersey 08731
SUBJECT:
Reportable Occurrence Report No. 50/219/80/8-lP The following is a preliminary report being submitted in compliance with the Technical Specifications, paragraph 6.9.2.a. Preliminary Approval:
, 6t-J. T/f ' Carroll, Ar.
Stapon Manageb/ Date: J- 19 -? O f) cc: -O Mr. Roger Boyd <h n a\ p
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- 9 Date of '.'erbal Cate of Notification: February 15, 1980 Occurrence: February 15, 1980
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Initial Written Time of Report Date: February 19, 1980 Occurrence: 0YSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Reportable Occurrence Report No. 50-219/80/8-lP IDENTIFICATION During verification of as-built conditions for piping hangers, 0F OCCURRENCE: it was noticed that nine (9) pipe clamps on piping to the isolation condensers were not properly installed. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a.(9). CONDITIONS PRIOR Steady State Power Routine Shutdown TO OCCURRENCE: Hot Standby Operation Cold Shutdown Load Changes During X Refueling Shutdown Routine Power Operation Routine Startup Other (Specify) Operation Reactor subcritical. Reactor mode switch locked in refuel. Cavity flooded. DESCRIPTION On Friday, February 15, 1980, during the inspection required for 0F OCCURRENCE: IE Bulletin 79-14, nine pipe clamps were discovered improperly installed. The clamps which connect snubbers to pipe to the isolation condensers were not welded to the pipe. -The snubbers, as referenced by Bergen-Patterson Drawing, are numbered: N 632R1 633R1 -) \ 632R2 632R3 633R2 633R3 t/(\ t, } f 632R4 633R4 .O -
- 632R7 APPARENT CAUSE Design Procedure s
,O 9((j d 0F OCCURRENCE: Manufacture Installation / Inc. Environmental f\ 1 X
Construction Unusual Service Condition Component Failure Operator Other (Specify) The pipe clamps were not welded to the pipe.
a ? Report 3ble Occurrence Page 2 Report *:o. 50-219/50/8-lP ANALYSIS OF The snubbers are attached to the pipe clamps in three different OCCURRENCE: methods. One method is connecting the snubber line of direction through the center line of the pipe. This method does not require welding of clamp to the pipe because no sliding can occur. The other methods of attachment are axial and torsional. These two nethods require welding of the clamp to the pipe because there would be a possibility of the clamp sliding during a seismic event. The purpose of the Isolaticn Condenser System is to depressurize the reactor and to remove reactor decay heat in the event that the turbine generator and main condenser are unavailable as a heat sink. The system consists of two loops, each capable of accomplishing the purpose of the system. CORRECTIVE To be determined at a later date. ACTION: FAILURE DATA: N/A Prepared by: N '/ Gary Hinrichs fo - Date: 2//7/$o
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' Occurrence: February 20, 1980
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7 Initial Written Time of 1 Report Date: M :50 p.m. l
'. . , . Occurrence:
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- OYSTER' CREEK NLIC. EAR GENERATING STATION ~- 3 FORKED: RIVER, NEW JERSEY 08731 "N
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Reportable Occurrence Report;No. 50-219/80/.10-lP - . .y. j y ., ! a IDENTIFICATION During verification:of as' built conditions for' pipe hangers, it - -) 0F OCCURRENCE: was noticed that three pipe hangers in the Liquid Poison Systes ! were not properly installed. '
, j This event is considered to be a reportable occurrence as defined '
in the Technical Specifications, paragraph 6.9.2.a.(9). Steady State Power Routine Shutdown CONDITICh5 PRIOR TO OCCURRENCE: Hot Standby Operation Cold Shutdown Load Changes During X Refueling Shutdown Routine Power O
. Routine Startup Other (Specify)peration -
Operation- - Reactor subcritical.
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Reactor mode: switch locked in refuel.. D D'
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p . ., p.; g ; . . DESCRIPTION ~ On Wednesday, February 20, 1980, at approximately"3:50 p.m.',
$0FOCCURRENCE: during.the inspection required for IE Bulletin 79-14, three pipe M' . ' '
hangers:were discovered improperly instal. led. The pipe hangers that restrain a. vertical section are numbered NP-2-RBA,'HP-2-R88
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and MP-2-R9. These hanger numbers are referenced on.Bergen- _ ~' Patterson Drawings.. *
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- - Alco a. restraint . ND-1-R2. on the return line of the cleanup
- systas.was of the' incorrect design. The systen requires restraint
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Y of the pipe in tmo directions and ND-1-R2 was.onigt,apable of one y 3,.f - .g+ v. directional re-traint. ,., i.df ~
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- APPARENT CMSE , " ' Design '-
Procedure W'- DOCCURRENCE:.: . - Manufacture Unusual Service Condition
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-Component l'ailure (,?
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..n... . - ~ . - . . - . . .. Y N ,j.$$i? The P pe ha.pgers. were impropi;1y. installed. i f-- - \.) q)r 1l
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Page 2 ; p 3.-. P.eportable Occurrence 7 Peport No. 50-219/80/10-1P . ~ a . r
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. M AMLYSIS OF The pipe hangers are used to restrain a pipe frta exi:essive 1 movement during a seismic event. The three hangers all provide ;
OCCURRENCE: horizontal restraint on the vertical pipe... The hanger which : ; consists of a pipe clamp with two lugs welded on the outside of I the clamp 90' frontthe pipe clamp end should rest.'.in a square 'ecx a made of angle imn.. The four equidistant external. points should p rest on-the centerof theeflats of the box. The box is! rigidly :I
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e supported to'the drywell wall. .Therefore, if pmperly installed. the pipe would~ be' allowed minimal horizontal movement.: The ; r hangers were found with the pipe clamp located above the restraining , , box which would' pennit excessive movenent of the pipe in a seismic f 1 event. The Liquid Poison System is a standby, redundant, independent control system for use i;* the unlikely event that the. control rod systen is inoperable. The Liquid Poison System is actuated only by renote manual action from the Control Room and will be used only during extreme emergency conditions. The cleanup system is a filtration and ionization exchange system
- for maintaining the purity of the water in the reactor vessel and recirculation lines. The restraint in the return line was only capable.of restraint in one direction, therefore. the pipe 1 restraint would be considered inoperable in a seismic event. j
- : L CORRECTIVE? The hangers in:the: Liquid Poison System were properly reset in ~ ~
j ACTIOR:..x the boxes. .4 i The restraint' in the cleanup system is under a des ~ign review to correct the deficiency. : cg. : . - a
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