ML20034C657

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Summary of 900419 Meeting W/Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Supporting Info Encl
ML20034C657
Person / Time
Site: Summer 
Issue date: 05/03/1990
From: Hayes J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9005040290
Download: ML20034C657 (15)
v • d • e


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Mah3,1990 o

i Docket No. 50 395 LICENSEE: South Carolina Electric & Gas' Company I

FACILITY: V.C,SummerNuc%arStation,UnitNo.1

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SUBJECT:

SUMMARY

OF APRIL 19,1990 MEETING WITH SOUTH CAROLINA ELEC %IC & GAS COMPANY l

I GENERAL GnAril$9(NRR)metwithrepresentativesoftheSouthCarolinaElectric 1990, a representative of the Office of Nuclear Reactor Regu ati n Q

& Gas Cmnpany (SCE&G) to discuss the status of the licensing issues for the V. C. Summer Nuclear Station and their requested approval to incinerate Jenkinsv111e, South Carolina.g was held at the V. C. Sumer Station in contaminated oil. The meetin A list of those persons who attended the maeting is included as Enclosure 1.

DISCUSSION A handout was provided at the meeting which presented the NRC's current assessment of the status of.various licensing actions. This handout is included as Enclosure 2.

Discussions were 'mid on the results of the of the eddy current testing of !Aa steam generators a9d the request for apsroval to incinerate contaminated orl.

It was indicated to SCE8G that the su)mittal for approval of incineration of contaminated oil needed additional information before it could be evaluated and that a ifqonse amendment was required. contains a status report of the eddy current testing as of April 19, 1990. Enclosure 4 is a handout provided by the licensee which indicated the licensee's assessment of priortties of licensing actions and items which are being worked by either the NRC'or SCE8G.

Ofignal signed by:

John J. Hayes, Project Manager Project Directorate :11 1 Division of Reactor Projects. 1/11 Office of Nuclear Reactor Regulation

Enclosures:

As Stated cc w/ enclosures:

See next page 9005040290 900503 Ok DR ADOCA 0500g5 P

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/90 OFFICIALRECORDC[PY Document Na% r SUMMER

SUMMARY

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Mr. O. S. Bradham South Carolina Electric & Gas Company Virgil C. Sumer Nuclear Station 1

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Mr. R. V. Tanner l'

Executive Vice President S.C. Public Service Authority P. O. Box 398) l' Moncks Corner, South Camlina 29461-0398 J. B. Kn ot ts, Jr., E sq.

Bishop Cook, Purcell and Reynolds 1400 L St reet, N.W.

Was hington, D. C.

20005-3502 Resident Inspector /Sumner NPS

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c/o ll.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Caroline 29065 Regional Administrator,s Region II U.S. Nuclear Regulato'ty Comission, 101 Ma rietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P. O. Box 293 Winnsboro, South Carolina 29180_

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Mr. Hepard G. Shealy, Chief

_i Bureau of,Radi0109ical Health

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South Carolina Department of Health i

and Environmental Control i

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Colunbia, South Carolina 29201 4

South' Carolina Electric & Gas Conpany Mr. A. R. Koon, Jr.. Manager ibclear 1.imnsing Virgil C. Sumer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065 c

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s STATUS OF NRC TACS FOR THE V.

C.

$UMMER PLANT April 3, 1990-i 49976 Itf PROCRAM (M.

NUME)

  • ! TEM NOW GIVEN LOW Pkl0RITY.

53720 litM 2.2 of CL 83*28._10UIP. CtattlFICAfl0N AND i

VENDOR INTERFACE FOR SAFETY RttATED COMPONENTS (SCOTT NEWBERRv X*20787)

  • ftR 18$UED BY tG40
  • 0 PEN ITEM $ ARtt
  • CONTACT VENDOR $ Of KtY COMPONENTS $UCH A$ AFW PUMPS, ECC$ PUMPS SAFETY RELAftD BATTER!!$,

AND $AF8TY RtLATED VALVES TO FACILITATE THE EXCHANGt OF CURRENT ftCHNICA[ INFORMAfl0N.

AN INFORMAL INTERFACE AGRitMINT $HOULD Bt ESTABLl8HED.

  • FOR DCs AND SAftfT RELAft0 SWITCHGEAR VENDOR $

A FORMAL INTERFACE $1MILAR TO THAT WITH THE NS$$ $HOULD BE E$fABLISHED.

  • CtWERIC LETTER TO Bt 18$UtD.
  • GENERIC LETTER WILL PROVIDE GUIDANCE ON VENDOR INTERFACE, LICEN$tt WilL BE REQUESTED TO CONFIRM BT LETTER THAN THtY Miti GL, AND NRC MAY INSPECT LICtW$tt'$ PROGRAM.

$3942 Ll[MS 4.2.3 $ 4.2.4 0F CL 83*28. PRfVENTIVE MflNTENANCF PROGRAM FOR RX TRIP BREAKERS, llFE T F S i l *J G 1 REPLACEMtWT (C. MORRIS X*23284)

  • BULLETIN l$ BilNG PREPARED TO SEND TO CRGR.

64821 R$8

$*i.

NATURAL CIRCULAfl0N TEST OF THE REACTOR i

COOLANT l

  • REACTOR $YSTEMS BRANCH TO REVIEW THl$ ITEM.

CONFERENCE CALL $ HELD 6/21/89, 7/19/89 AND 8/29/89..

  • $CHEDULE FOR $UBMITTAL BY LICEN$tt 15 12/89
  • $UBMITTAL MADE 1/25/90.
  • ADDITIONAL INFORMAfl0N PROVIDED 3/9/90.

68046 ist 12/23/87 PROGRAM REVis10N (K. DEMP$tY X*20918)

  • SER IS$UED 4/19/88

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  • SOME REllEF$ DEWlED. SOME GRANTED
  • LICEN$tt MUST ADDRES$ APPENDIX C OF THE TER WHICH COVERS OMIS$10N$ AND INCON$1STENCIES IN THE PROGRAM.
  • MttTING HELD 6/1/88 TO DISCUS $ RELIEF $ WHICH WERE DEWlED AND 12/23/87 REVISED PROGRAM.

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  • REvitED PROGRAM $UBMITTED BY $CERG 8/31/88.
  • ADDITIONAL INFORMAfl0N REQUt$TED VIA THE TELEPHONE ON 6/1$/89 FOR EG40 10 COMPLETE THE REVIEW.

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  • PROCEDURE GTP 302 TRANSMITTED BY LICEN$EE 7/19/89.

68610 1MPLEMENTAfl0N OF STAfl0W BLACK 0UT RULE. 10 CFR 50.63. A*22 (A. GILL) i

  • RESPON$E TRANSMITTED 4/17/89
  • REVI$tD RESPON$E TRAN$MITTED BY $CESG 10/2/89 I
  • RESPON$t $ENT FROM LICEN$tE 3/29/90 INDICATING THEY HAVE Mtf NUMARC 87 00 GUIDANCE AND THE CLARIFICATION LETTER TO THE NUMARC BOARD OF DIRECTOR $ EXCEPT FOR THE EFFECTS OF THE LO$$ OF VENTILAfl0N.

ARIAS i

EFFECTED ARE-(1) CONTROL ROOM AND, RELAY ROOM 00MlWANT ARIA 0F CONCERN TEMPERATURE' DETERMINATION AND (2) OPth!NG CABINET 000R$ IN THE MAIN CONTROL ROOM, i

68834 BULLET!N 88 05. NON* CONFORMING MATERIALS SUPPtlE0 i

BY PIPINC SUPPtlES. INC. AT FotSOM.

N.J.

AND WEST JER$EY

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j MANUFACTURING CO. AT WittlAMSTOWN.

N.

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B*104.

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  • RESPON$t $UBMITTED 9/13/88.
  • WRITTEN RESPONSE DUE 60 DAY $ AFTER COMPLETION OF ALL SCHEDULED ACTIONS.
  • lNSPECTION CONDUCTED BY SCE&G 10/88.

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  • LICENSEE SENT LETTER ON RESULT $ OF INSPECTION OF N0ZZLE PLATES ON 3/6/89.

69066 STEAM CENERATOR.

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(H. CONRAD)

  • ENVIRONMENTAL AS$t$$ MENT PUBLISHED IN THE FEDERAL REGISTER 10/88.

CONFERENCE CALL N2LD 10/25/88.-

  • PRELIMINARY REVIEW !NDICATES THAT ADDITIONAL

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INFORMATION l$ REQUIRED.

  • TECHNICAL STAFF REVIEW 10'BEGIN UPON RECEIPT OF ADDifl0NAL SCESG INFORMATION,
  • ADDifl0NAL INFORMAfl0N TRANSMITTED 6/13/89 l
  • MEEfikG NELD 10/5/89 WHERE IT WAS DETERMINED THAT ADDITIONAL INFORMAfl0N I$ REQUIRED 10 DEMONSTRATE THE ADEQUACY OF THE USE OF l

EDDY CURRENT TESTING To DETERMINE SG TUBE CRACK SIZE AND i

ORIENTATION.

  • AWAITING INFORMAT10W.
  • LETTER TRANSMITTED 1/12/90 INDICATED THAT ADDITIONAL INFORMAfl0N

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c WilL BE $U8MITTED 8/90.

e 69693 ButttTIN 88 08. " THERMAL STRtsttt IN PIPING F

CONNECTED 70 REACT 0k COOLANT SYSTEMS

  • RESPONSE $UBMITTED 9/29/88.
  • MEETING HELD 10/6/88.
  • ADDITIONAL INFORMATION $UBMITTED BY SCE80 12/19/88.
  • DIFFERENTIAL TEMPERATURE DATA $UBMITTED ON 3/23/89.

i 69782 GENERIC LETTER 88 17. "L0$$ OF DECAY HEAT REMOVAL" i

  • RESPONSE TO EXPEDIT10U$ ACTIONS PROVIDED BY $CESG 1/23/89.
  • RESPONSE TO 6 PROGRAM ENHANCEMENTS PROVIDED BT LICENSEE 2/2/89
  • NRC COMMENTS ON EXPEDITIOUS ACTIONS $ENT TO LICEN$tt 6/26/89.

7 69978 BULttTIN 88 04. POTENTIAt SAFETY RttATED PUMP L0tt.

  • WRITTEN RESPONSE DATED 7/8/88.

RESPON$E ON EFW PUMPS PROVIDED' 12/20/88.

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  • RESPONSE REQUIRED ON VMETHER IN$TALLED MINIFLOW CAPACITY l$ ADEQUATE FOR $1NGLE PUMP OPERAfl0W.

INFORWAtl0N TO BE PROVIDED FOLLOWING 1990 REFUELING OUTAGE.

71725 GENERIC LETTER 88*14. "lNSTRUMENT AIR SUPPLY SYSTEM PROBLEMS AFFECTING SAFETY RttAftD EQUIPMENTH RESPONSE SENT 2/2/89.

1 AFFECTED VALVES AND COMPONENTS TO BE ADDED TO THE PREVENTATIVE MAINTENANCE PROGRAM BT 4/28/89.

2.

PERIODIC DEWPOINT MON 1TORING AND $YSTEM BLOWDOWN AT SELECTED LOCATIONS INITIATED BY 8/1/89.

3.

FULL IMPLEMENTAfl0N OF>A QUALITY RELATED PROGRAM FOR DIAPHRAGM $ BY THE FIFTH-REFUELINC QUTAGE (4/90).

LETTER SENT TO LICENSEE ON 3/31/89 REQUESTING THAT.THE LICENSEE INFORM THE NRC VMEN ALL REQUIREMENTS ARE IMPLEMENTED.

I 72171 NRC BULLETlw 88 11. " PRESSURIZER SURCf LINE THERMAL STRATIFICAfl0NH l

LICENSEE RESPONDED 3/1/89.

$UBMITTED RESPONSE TO 1.A 0F BULLETIN.

LICEkSEE INTENDS TO WORK WITHIN WDG.

A L T E P. N A T E SCHEDULE PROP 0$fD FOR 1.8 0F BULLETIN.

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  • LETTtt StNT 6/12/89 DtTAILING AGREEMENT StTWttN NRC AND 1HE WESTINGN0Ulf OWNtts GROUP.

LICEN$tt$ Att To $UBMlf TNtlR RI$PON$t TO ITEM 1.b 0F THE BULLETIN WITHIN 1 YEAR AS ORIGINALLY Rt0VIRED.

  • RESPON$t TRANSMITTED TO ITEM 1.b 0F THE CL ON 1/3/90.

72893 FttDWATER It0LAfl0N Vatvts eft 3. 7. 1.6),

  • REQUEST $UBMifftp 4/5/89
  • $NOLLit0 5/3/89.

73300

$tRVitt WAftR $YsitM B10 CIDE TREATMENT

  • REQUtti FOR APPROVAL $UBMifftD 5/19/89.
  • CONFERENCE CALL 9/18/89 REQUESTED BET 2 $UBMITTAL TO EPA FOR f

REGl$fRATION OF THE B10 CIDE AND INE EPA RESPON$f BACK TO THAT REQUtsf.

  • COPY OF $TAff APPROVAL RfCtlVfD 11/14/89.

73713 GENERIC L(1TER 89 06, " TASK ACil0N PLAN ITEM !.D.2

  • RESPON$t TRANSM1)ft0 7/7/89
  • LICEN$tE TO TRANSMIT DESCRIPfl0N Of REVISED PROGRAM FOR OPERAfl0N TOLLOWING MARCH 1990 RtfUELING OUTAGE.

74475 GtWERIC triftR 88 20. "INDlVIDUAl PLANT EWAMlWATION FOR $tVERE ACCIDENT VUlNtRABillTY".

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  • RESPONSE DUE DUE 60 DAYS FROM FEDERAL REGl$ftR NOTICE ON AVAILABILITY OF NUttG 133$.
  • RESPON$t TRAN$NITTED 10/31/89.

LETTER SENT TO LICENSEE 1/12/90 STATING THAT LICEN$tt $HOULD CON $1 DER MORE THAN 5 CONTAINMFNT EVENT TREE MODis.

  • 3/23/90 LETTER FROM SUMMER le/ICAftD THAT THEY WOULD UTILIZE A DETAILED CONTAINMt41 (VENT Trit (CET) FOR CONTAINM[NT PERFORMANCE ANALYS!$ AND SOURCE TERM EVALUAfl0N.

Ctf WOULD NOT BE LIMITED 10 5 MODES.

SCt&G WOULD NOT LITERALLY APPLY IPEM METHODOLOGY.

ANALTS!$

10 Bt PERFORMED IN ACCORDANCE WITH THE GUIDANCE OF APPENDIX i 0F GL 88*20 AND NUREG*1335.

74822 TS 3.7.1.5 MSIV MODES 2/3 74823 18 SR 4.8.1.1.2.C DG FUEL Oil SAMPLING, ANALY$l$, ETC.

  • REVISED SUBMITTAL REQUIRED.
  • $HOLLlED 1/10/90.

F 75004 GtNERIC LETTER 89 19, *$AftTT IM>LICATIONS OF CONTROL STSTEMS IN LWR I

NUCLEAR POW (k PLANT $a (K. JAB 00VR X 21496)

LICEN$tt TO PROVIDE ST 3/20/90 $CHEDULt FOR.lMPLEMENTING RECOMMENDAfs0NS IN ENCLOSUtt 2.

COMMITMENTS MADE $NOULD Bt IMPLEMENTED PRIOR TO $TARTUP AFTER THE I

Flk$f REFUELING OUTAGE SEGlWWING 9 MONTH $ AFftR THE RtttlPT OF THE CL. (9/91 FOR SUMMER)

  • RtlPON$t TRAN$MifftD 3/19/90 STATlWG THAT $UMMER MEET $ THE CL.

i 75360 TS 4.7.15, MslV sTR0Kt flMt TEST

  • $HOLLIED 1/10/90.

i 75723' GENERIC LETTER 89 10, *$AftTT RELATED MOV TESTING AND SURVEllLANCtX

  • RESPON$t SENT 12/22/89.

CL0$t0UT 7/94, t

75877 AMENDMENT ON INCINERAfl0N OF CONTAMINAftD.Olt APPLICAfl0N MADE 1/4/90.

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BULLtTIN 87 02. SUPPLEMENT 1.

" FASTENERS TESTING 10 j

-DEffRMINE CONFORMANCE APPtfCABLE MATERIAL SPECIFICATIONS" RESPON$E SUBMITTED 7/20/88.

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LOS$ 0F FILL =0ll IN TRANSMITTER $ MAkUFACTURED BT RosEMOUNTS (BULLETIN 90 01) la.

CONFIRM ITEMS 1*5 0F REQUESTED ACTIONS ARE COMPLETED.

ib.

IDENT!FT INDICATED MANUFACTURER, MODEL STSTEM TRAN$MITTER WAS UTILI2ED IN, APPROXIMATE AMOUNT OF TIME AT PRESSURE, CORRECTIVE ACTIONS TAKEN AND DISP 051110N OF ROSEMOUNT MODEL 1153 8 & D AND 1154 THAT HAVE EXHIBITED STMPTOMS INDICATIVE OF LOS$ OF Oil AND HAVE BEEN CONFIRMED 10 HAVE EXPERIENCED LOSS OF FILL Oll.

I 1c.

IDENTIFT f"$ TEM !N WHICH 1153 B & D AND 1154 TRANSMITTERS, FROM MANUFACTUk;NG LOTS IDENTIFitD BT ROSEMOUNI-A$ HAVING A HIGH FAILURE TRACTION DUE TO LOS$ OF FILL Oll, ARE UTisIZED AND PROVIDE A SCHEDULE FOR REPLACEMENT FOR THOSE WHICH ARE IN REACTOR PROTECTION ST$TEMS AND THOSE WHICH ARE IN E$FA$.

2.

REPORT SUBSEQUENT 1153 8 & D AND 1154 TRAN8MITTER FAILURES.

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RELAXAfl0N OF STAFF POSITION IN GENERIC LETTER 83 28, litM 22, PART 2 avtNDOR INTERFACE FOR SAFETT RELATED COMP 0NENT$a, GENERIC LETTER NO. 90 03.

I

  • RESPON$t Rt0Ulkt0 FROM LICEN$tt BY 9/27/90 THAT LIC(NStt NA$

IMPLEMENTED:

(1)

PROGRAM WITN NS$$ VENDOR At DESCRIBED IN VETIP WHICH.

COVERS ALL $ Af TTY REL Af t0 COMPONENTS WITHIN NS$$ SCOPE OF SUPPLYl AND (2)

PROCRAM OF PERIODIC CONTACTS WITN VENDOR $ OF OTHER KEY SAFETY RELATED COMPONENT 4 NOT INCLUDED IN (1) ABOVE.

TACS CLOSED-LAL Egg DtstRIPfl0N OF THE TAC Daft CL0tti 51606 RV AND sv TESTlWG (!!.D.1) 1/19/90.

$$344 PROCEDURts GENERATION PACKAGES 2/26/90

$UPPLEM!NT 1 NUREG 0737) 53720 PART 1,

ITEM 2.2 0F GL 83 28, t0UIP.

3/20/90 CLA$$1FICAfl0N FOR SAft1Y RELATED COMPONENTS 59402 40 YEAR OL LIFE AMENDMENT 1/3/90.

71360 NRC BULLETIN 88 10 "NON* CONFORMING 3/29/90 MOLDED

  • CASED CIRCUlf BREAKER $"

72702 RE$1N,1NTRUS10N EVENT 2/89 3/9/90 74068 GENERIC LETTER 89*13, " SERVICE WATER 2/21/90 SYSTEM PROBLEM $ AFFECTING SAFETY RELATED (QUIPMENT".

74538 GENERIC LETTER 89*21

" REQUEST FOR 3/19/90 lNFORMAfl0N CONCERNING STATUS OF IMPLEMENTAfl0N OF UNRESOLVfD SAFETY 186UES (US1) REQUIREKINTS" 74559 RELIEF REQUEST ON MAIN SitAM DRAIN 12/14/89 VALVES, ASME SECTION XI.

74564 B U L I. t f l N 89*03, " POTENTIAL LOSS OF 1/21/90 REQUIRED SHUTDOWN MARGIN DURING REFUEllWG OPERAtl0NS" 74577 F*

EXTENSION 2/23/90 74578 LOSS OF OFFSITE POWER EVENT 7/11/89 2/21/90 74735

-GENERIC LETTER 89 07, " POWER REACTOR 1/22/90

SAFEGUARet CONilNGENCY PLANNING FOR SURFACE VEMICLE BOMBt".

74821 RENUMBERlWG OF 3/4.7.11 2/12/90 74824 18 3/4.5.2 REMOVAL OF RNR SYSTEM 3/6/90 AutoCLOSURE INTERLOCK (ACl) 74825 15 3.8.1 & 3.8.2 00 FUEL CIL STORACE 2/12/90.

VOLUMt 74826 18 1 ABLES 2.2 1 & 3.3 4,

REPLACEMENT 3/15/90 OF RTDs FOR RfD BYPAS$ MANIFOLD 74839 15 4.4.5.4 50 TUBE stEtVtt, B8W 3/22/90 75049 TS ON DELETION OF CYCLE SPECIFIC 3/6/90 PARAMETER $

75061 REQUALIFICA110N SCNEDULE 2/28/90 75359 1$ 3/4.3.3.6, TABLES 3.3 10 AND 4.'.7, 2/12/90 3

RS/RNR SUMP LEVEL 75361 1s 4.0.2, 3.25 SURVEILLANCE flME LIMIT 2/12/90 75953 REQUtst FOR APPROVAL to USE SB 166 3/5/90 74318 BULLETIN 89 02, "tTRESS CORRost0N 10/27/89 CRACKING OF MIGN MARDNESS TYPE 410 STAINLESS STEEL INTERNAL PRELCADED BOLTING IN ANCHOR DARLING MODEL 350 W SWING CHECK VALVES OR VALVES OF SIMILAR DESIGN".

ltems which have been closed out since the test licensing status meeting.

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4 Steam Generator Tube Eddy Current Inspection Status Report Date: 04/19/90 Time: 07:00 S/G

'A' S/G

  • B*

S/G

  • C*

l Number l 4 l Number l % l Number l % l I

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l Analyzed Final l

4394 l100l 4167 l100l 4370 l100l l-1 i

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l l Total Degraded l

295

')'6%l 387 l 9%I

'192 l 4%l I

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l-I

'l I-I l Total Number for l

l, %l l

l l

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l Eng. Evaluation l

0 l

0 l

%l 0

l-

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l_

l l

l l__-

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l Number l

l l.

l

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l l

l to be Plugged

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35 l12%l 49 l13%l 76 l40%l 1

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l I.___l l

l l Number l

l l

l l

l l

l to be Sleeved l

125 l42%l 108 l27%l N/A l

l 1

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I Number F* Applied l

135 l46%l

~230 l60%)

116 l60%l l

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  • Number to be Sleeved
  • indicates those tubes which could potentially be sleeved.

The final sleeve population will be determined at the conclusion of sleeve installation.

The current target sleeve number for A & B steam generators is 100 sleeves each.

    • Percent for degraded is percent of total tube population **
      • Percent shown for sleeve, plua. or F* is percent of degraded for that generator ***

Steam Generator

  • A*

- 12 sleeves expanded - 2 with' connector tubes-stuck ~ NDE for 10 is to begin this A.M.

Steam Generator *B * ~ Plug Removal in progress ~ 14 of 34 plug already removed.

Steam Generator *C'

- - Set-up for PAP installation this A.M.

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Enclosure'4' High Priority ~ Items for NRC' Review i

1.

TS A.7.15, MSIV Stroke Time Test (75360)

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2.

Amendment on Incineration of Contaminated Oil 3.

TS 4.8.1.-1.2.c, DG Fuel Oil Sampling, Analysis,_etc.

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TS 3;7.1.6, Feedwater Isolation Valves Modes 2/3 (?2893)-

1 8

5.

TS 3.7.1.5, MSIVs Modes. 2/3 (74822) l i

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Other Items Being Worked by NRC

'ISI Program Review (49976) e Items 4.7 3 and 4.2.4 of GL 83-28, Preventive Maintenance s

Program for Reactor Trip Breakers...

URC is preparing a bulletin.

(53942)

RSB5-1, Natural Circulation Testing (64 821) e Awaiting Olosure IST Program Review (68046) i Implementation of Station Blackout Rule (68610) e Bulletin 88-05, Non-Conforming Materials (638834) e Generlo Letter 88-~17, Loss of De' cay Heat Removal Generic Letter 89-19, Safety Implications of Control 8

Systems...

(75004)

Awaiting Closure Bulletin 87-02, Supplement a

Conformance Applicable Material Specifications 1, Fasteners Testing to Determine Response Submitted July 20, 1988

E Items Being Worked by Licensee Steam Generator L* (69066)

Additional information to be submitted by August 1990, Generic Letter 90-03, " Vendor Interface for Safety Related i

Components (See 53720 Response is due by September 27, 1990 Bulletin 88-04, " Potential Safety Related Putap-Loss" (69978) s Response is due after Refuel V.

Generlo Letter 88-14, " Instrument Air System" (71725) 8 Response required when all requirements are met.

Generic Letter 89-06, " Task action Plant Items I.D.3-SPDS" s

(73713)

Response is due after Refuel V.

Generic Letter 88-20, "IPE" s

SCE&G is developing "IPE."

Bulletin 90-01, "Rosemount Transmitters" Response due by July 20, 1990.

Bulletin 88-11, " Pressurizer Surge Line Thermal t

Stratification" Response due by January 31, 1991.

Generic Letter 89-10

" Safety Related-MOV Testing..."

e (75723)

Implementation in progress through July 1994.

Bulletin 88-08, " Thermal Stresses in Piping Connected to RCS i

(69693) i l

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t-s' DISTRIBUTION 80edoed8Wer Centra 1 File l

EC PDR Local PDR T. Harley 12-G-18 F. Nirag 11a 12-G-18 J. Pa rt low 12-D- 9 E. Adensam 14-B-20 P. Anderson 14-B-20 J. Hayes 14-B-20 OGC 15-B- 18 E. Jordan MNBB-3302 ACRS(10)

P-315 B. Borchardt 17-G-21 e

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