ML20058G434

Summary of 901016 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Actions for Facility

ML20058G434
Person / Time
Site:	Summer
Issue date:	10/31/1990
From:	George Wunder Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9011130142
Download: ML20058G434 (16)

Text

{{#Wiki_filter:_ October 31, 1990 Docket Noo 50.,195 LICENSEE: South Carolina f.lectric and Gas Company FACILITY: V. C. w mmer Nuclear Station, Unit No. 1

SUMMARY

OF OCTOBLR 16, 1990 MEETING WITH SOUTH CAROLINA E! 7TRIC AND GAS COMMNY GENERAL On October 16, 1990 representatives from South Carolina Electric and Gas Company met with representatives of the Office of Nuclear Reactor Regulation (NRR)forthepurposeofdiscussingthestatusoflicensingactionsforthe V. C. Summer Nuclear Station, Unit No. 1. The meeting was held at the NRR office in Rockville, Maryland. A list of those individuals who attended the meeting is included as Enclosure 1. DISCUSSION A handout was provided at the meeting which presented the NRC's current assess. ment of the status of various licensing actions. 1his handout is included as. During the meeting the licensee presented t.dditional information as justification for their technical specification change involving the pres. surizer safety valve setpoint tolerance level of plus/minus three percent. This information was included in a handout marked here as Enclosure 3. The licensee also presented their li est organizational chart along with a pictorial of t1eir Vice Preside... Nuclear Operations and the general managers who report to that officer. These are marked as Enclosures 4 and 5, respectively. The licensee also presented a listing of the technical specifi-cation changes that they intend to submit during the next six months. This is included as Enclosure 6. Currently, of those to be submitted only the ZIRLO change is needed for the refueling outage scheduled for September 1991. Original Signed By: George F. Wunder, Project Manager Project Directorate 11-1 90111301429$$$$$93 Division of Reactor projects - I/II DR ADOCK 0 PNV E Office of Nuclear Reactor Regulation

Enclosures:

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Hr. John L. Smolds South Carolina Electric & Gas Company Virgil C. Sunner Nuclear Station CC: Mr. R. V. Tanner Executive Vice President S.C. Public Service Authority P. O. Box 398) Moncks Corner, South Carolina 29461-0398 J. B. Knotts, Jr., Esq. Bishop. Cook, Purcell and Reynolds 1400 L Street, N.W. Washington, D. C. 20005-3502 Resident inspector / Summer NPS c/o U.S. Nuclear Regulatory Connission Route 1, Box 64 l Jenkinsv111e, South Carolina 29065 Regional Administrator, Region 11 U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlant6, Georgia 30323 Chairman, Fairfield County Council P. O. Box 293 Winnsboro. South Carolina 29180 Mr. He)vard G. Shealy, Chief Bureau of Radiological' Health South Carolina Department of Health and Environnental Control 2600 Bull Street Columbia, Scuth Carolina 29201 South Carolina Electric & Gas Company Mr. A, R. Koon, Jr., Manager Nuclear Licensing Virgil C. Sumer Nuclear Station P. O. Box 88 Jenkinsv111e, South Carolina 29065

,--.e,.... ENCLOSURE 1 ATTENDANCE LIST OCTOBER 16. 1990 SCE&G NRC A. Koon, Jr. E. Adensam W. Higgins L. Cohen G. Hanner J. Hayes, Jr. t C. Hsii D. Terao R. Van Niel

SFIWIUS OF NFC TACS FOR M V. C. SLDNER FINC October 16, 1990 49976 ISI HOGRAM (G. JOHNSCN) 53942 JTDtS 4.2.3 & 4.2.4 OF GL 83-28. PREVDfrIVE lfg2{IDWICE HOGRAM FDR RX 'IRIP EREAKERS, LTTE TESTING & REPIACEMDff (C. KRRIS X-23284) -NJLILTIN HAS BED 4 PREPARED 'IO SDO 'IO CRliR. 68046 IST 12/23/87 MCGRAM REVISION (K. IIMPSEY X-20918) -SER ISSUED 4/19/88 -SCHE RELIDS DENIED, SWE GRANTED -LICDiSEE WST ADtRESS APPDOIX C OF M TER WHICH CDVERS'CHISSIONS AND DKDNSISTENCIES IN ' DIE ISOGRAM. -MEETING HEID 6/1/88 'IO DISCUSS RELIEFS WHIM WERE DDUED AND 12/23/87 REVISED MCGRAM. -REVISED PROGRAM SUIMITIED BY SCE%G 8/31/88. -ADDITIONAL INFORMATION REQUESTED VIA THE TEIDHNE ON 6/15/89 FOR D%G 'IO CIMPILTE 'INE REVIDf. -PROCEIURE GTP 302 'IRANSMITTED BY LICINSEE 7/19/89. 68610 IMPUXDfrATION OF STATION BIACKCUT RUII,10 CFR 50.63. A-22. (A. GILL) -RESFONSE TRANSMITIED 4/17/89. -REVISED RESPONSE 'IRANSMITTED BY SCE&G 10/2/89 -RESPONSE SDff FRCH LICENSEE 3/29/90 INDICATING 'IHEY HAVE MET NUMARC 87-00 CUIDANCE AND M CIARIFICATICH IEITER 'IO THE NUMARC ICARD OF DIRECIORS EXCEPT FOR 'IHE DTECTS OF M LOSS OF VDfrIIATION. AREAS DTECIED ARE (1) C0ffIROL ROW AND RELAY ROW DWINANT ARFA OF CONCERN TEMPERNIURE DETERMEDLTION AND (2) OPDUNG CABINET DOORS IN 'IHE MAIN 00tfDCL ROOM. -SE '!O BE ONPIETED 6/30/91. 69066 STEAM GDERNItR. L* (H. CENRAD) -D4VIRONMDfrAL ASSESSMDC PUB 12SHED IN M FEDERAL RDGISTER 10/88. -OONFERENCE CALL HELD 10/25/88. 4RELIMDDRY REVID4 INDICATES 'IHAT ADDITIONAL l l

l INitRRTICH IS RICUIRED. %MCAL STAFF REVIDi '!O HEDIN Ulm REGIPT OF ADDMCIE SCDG INPG99&ICN. -ADDITIONAL INFG99& ION TRANSMITIED 6/13/89. -MELTING HEID 10/5/89 WHERE IT WAS DETERUNED DAT ADDITICHAL INFVRRTICN IS REQUIRED TO ID0NSTRAIE THE AIEQWCl OF THE USE OF EDDY CURRDE 7ESTING TO IEIntCNE SG 'IUBE CRAG SIZE AND CRIDEATICN. -IEITER TRANSCTIED 1/12/90 INDICATING THAT ADDITICNAL DATA WIIL E SUIMITIED 8/90 ADGUESDC NRC QUISTICNS. -REVISED SUIMITIAL MAIE 8/30/90. 69693 IUusTIN 88-08. " THERMAL p CES IN PIPING 00tNECTED TO REAC'ICR CODIANT SYSTDE -RESKHSE SUIMITIED 9/29/88. -MEETING HEID 10/6/88. -ADDmot&L INFUORTICH SUEMITTED BY SCDG j 12/19/88. J -DIFFERDUIAL 2D@ERATURE IWIA SUIMITTED CN 3/23/89. P 72893 TEEDWATER ISOIATION VALVES (TS 3.7.1.6) -RDQUINT SUIMITTED 4/5/89. -SIOTLim 5/3/89. -74475 GDERIC IETIER 88-20; " INDIVIDUAL PIANT EXAMINATICH IDR SEVERE ACCIDENT VUI.NERABILITY". -RESKNSE IUE 60 DAYS FRN FEDERAL RDGISTER NC7TICE ON AVAIIABILITY OF NUREU-1335. -RESIONSE TRANSMITTED 10/31/89. -IflTER SDC 70 LICENSEE 1/12/90 FIATING 7 HAT LICENSEE SHCUID CONSIDER MDRE 7HAN 5 CDtfrAINMENT EVDE TREE NOCES. -3/23/90 IEITER FRCH S(DMER INDICATED THAT THEY WOUID UTILIZE A DETAILED CONTADNDE EVDC 'IREE (TT) FOR 00tf1AINMENT PERFORMANCE ANALYSIS AND SOURCE TERM LVAIIRTION. CET WOUID ICT BE LIMITED 70 5 PODES. SCE&G WOULD }CT LITERALLY APPLY IPEN MEIN 0DOIDGY. ANALYSIS TO BE PERFORMElt IN ACCORDANCE WITH THE GUIDANCE OF APPENDIX 1 OF GL 88-20 AND }URED-1335u -SUPPIJNDR 2 ISSUED 4/4/90. 74822 TS 3.7.1.5 MSIV MXES 2/3

e f 74823 TS SR 4.8.1.1.2.C DG PUEL OIL SAMPLDC. ANALYSIS. EZg,i. -I'!IM SHOLUID 1/10/90. -REVISED SE SUIMITIID BY UCENSE 4/10/90. 75993 GENERIC SAFTTY MUE MIDTICN. GENERIC IETIER 90-04 4tET WIDI LICENSE CN 6/25/90. -RESKNSE SDff BY UCINSE 6/29/90. 76618 1 DSS OF FILirOIL DJ 'IRANS>unucis MANUFACIURED BY 10SDt1NIS (IKTLETIN 90-01) 1a. CENTDM IIINS 1-5 OF RIQUESTED ACTICNS ARE CXMP2IED. Ib. IDENTITY INDICATED MANUTACIURER, MXEL (, SYSTD4 'IRANSHITIER WAS UTIUZED IN, APPROXDRTE APOUNT OF TDE AT PRESSURE, 00RRDCTIVE ACTICNS TAKEN AND DISICSITICN OF ROSDOUNT MODE 1,1153 B & D AND 1154 DRT HAVE EXHIBITED SYMPItNS DOICATIVE OF 106S OF OIL AND 1RVE WEN CCNFIRMED 'IO HAVE EXPERID4CED 10SS OF FILL OIL. Ic. IDDfrIFY SYSTD( IN WHICH 1153 B & D AND 1154 'IRAnSKITTERS, IRCH MANUFACIURDC IDIS IIINTIFIED BY ROSDOUNT AS HAVDC A HIGi FAIIURE FRACTICH DUE 'IO IDSS OF FILL OIL, ARE UPILIZED AND PROVIIE A SO{EDUIE FCR REPLACENDft FCR 'IHOSE WHIO! ARE IN REAC'ICR }RCTTECTICH SYSTINS AND 'IHOSE WHIO! ARE IN ESTAS. 2. RER3RT SUBBIQUDff 1153 B & D AND 1154 'IRANSHITTER FAIIURES. -RESE0NSE 'IRANSHITTED 7/19/90. (1 a d. r.,1 T<aw.w 8 % iJ col 4'o ', ' ', ",, ( Q@u' n[ f 0 76708 REIDCATICN OF 'INE IDF Q \\.1 i* -SUIMITIAL MADE 4/18/90. 4 -MEETING HELD WTIN LICENSE AT SITE 6/25-26/90. -SUPPIIMDirAL INFDFf% TION SUIMITTED 8/1/90. 76867 FRESSURIZER SAFETY VALVE SETPODff +/- 3%. i -SUIMrITAL MADE 5/16/90. 76977 RD(WAL OF RDTIRED SHl.TITUN MARGIN CURVE FRCN TS AND PIACEND7P DTIO 'IME CDI&, -SUIMITIAL Wrni 'IS ORNGE MADE 7/18/90.

77135 RESOII7rION OF IUTIPTIN 79-02 AND 79-14 Dem;nOiS -RESKNSE IUE fBCM 'IHE 'IY)ONICAL NENOf 10/30/90. 77220 rs f rrIG4 OF PSRC MDNM TITrM AND N0@5R FRG( 'IS 6.5.1.2. -SUBGTIAIS MADE 7/18/90 AND 8/32/90. -REVISED SURCITAL RD@JIRED. Al 1)St% 77384 G9fERIC IEPER 90-06 "RESOIITTION OF GDfERIC WUE 70..'h0WER OPERATED RPTTEF VALVE AND BIDCK VALVE RPf TABIllTY' -RESKHSE DUE 12/20/90. -TS M3DIFICATION DUE 'IO 'IHE NRC BY 'IHE DiD OF 'IHE REFUEL 6 OUTAGE. 77459 GDfERIC'IEPTER 90-06. "GDIERIC ISSUE 94. ' ADDITIONAL IDW-TDiPERATURE OVERTHESSURE Ihnu;nON FOR LIGff WATER REACIORS' -RESKNSE IIJE 12/20/90. 'IS EDIFICATIQi DUE 'IO 'DE NRC BY 'IHE DO OF 'IHE REFUEL 6 OUIME. 77706 ISI PrfTrF ON VOI1Ff1RIC EXAMDMTION OF SG 'IUBE SHEEP Wrim -SURCITAL MADE 9/25/90. 7 I l' 77733 IST RPf TEF ON RHR 03tfrADMENT ISOLATION VALVES XVG 8701 A/B -SURGTTAL MACE 9/28/90. 1775b 7M77 BLVIEW OF WKKwnVE ACTIONS 'IO ACTION C.2 OF IUTJPTIN 88-02 -INIMMATION PROVIDED BY SCE&G 6/13/90. ????? BJLLETIN 87-02. SUPPID1DTP 1. "FAffrDfERS TESTDC 'IO DEITRKINE OJNFORMANCE APPLICABIE MATERIAL SPECIFICATIONS" -RESPONSE SURGTED 7/20/88. l l. l' l l l

TACS m m IAQ LQ, DESGIPTICH OF 'IHE 'IAC DPdT CLDSED 51606 RV AND SV TISTDC (II.D.1) 1/19/90. 53720 PART 1, I'IDI 2.2 Or GL 83-28, E3JIP. 3/20/90 CIASSITICATION "A SAFLTi REIATED CDGWDfIS 55344 PROCE2URE GDERATICN PACKAGES 2/26/90 SUPPIlMDff 1, NURED-0737) 59402 40 YEAR OL LIFE AMENINENT 1/3/90. 64821 RSB 5-1, NAIURAL CIRCUIATION 'IE!rr OF 8/6/90 THE REACKR C001Nir 68834 BUIlETIN 88-05, NON-CD&DRMDG 5/7/90 MATERIALS SUPPLIED BY PIPDG SUPPLIES, INC. AT FDISCH, N.J. AND kTSP JERSEY MA!UFACIURDG CD. AT WILLIAMS"ICWN, N. J., B-104. 69782 GDERIC IEITER 88-17, "1 DSS OF DECAY 7/11/90 HEAT RDCVAL" 69978 NJIIETIN 88-04, ICIDfrIAL SAFLTV 8/31/90 REIATED REP ICSS. 71360 NRC NJLLETIN 88-10, "NON-CDUDRKDG 3/29/90 !OIDED-CASED CIRCUIT BREAKERS" 71725 GDERIC IEITER 88-14, "INSIRUMDff AIR 9/13/90 SUPPLY SYSTEM PROBIINS Arru. tug SAFLTi-REIATED EgJIINDff" I 72171 NRC BULTF G 88-11, " PRESSURIZER SURGE 8/30/90 LINE h,%L SIRATIFICATICN" 727v2 RESIN INIRUSION EVENT 2/89 3/9/90 73300 SERVICE WATER SYSTEN BIOCIDE 7RFATMDfr 4/6/90 ( 73713 GDERIC IEITER 89-06, " TASK ACTICH PIAN 4/27/90 l ITIN I. D. 2 - SPDS".. l 74068 GDERIC IEPTER 89-13, " SERVICE WATER 2/21/90 I-SYSHN PROBI1NS Artu. tug SAT 1T. i REIATED EQUIINENT". l l l m2.-a-A. y e w. v-9

TACS mtv:m IAC & IESGIPTION OF DE TAC DATE CIItED 74318 HJLIETIN 89-02, "S7RESS CORIGION 10/27/89 GACKDG OF HIGi MARINESS TYPE 410 SIAIN1ESS S'IEEL INIERNAL PREIIAIED ICLTDC 1N ANOtCR IARI2NG ML $30 W SWDC WDCK VALVIS CR VALL OF SIMIIAR IESIQi". 74538 GENERIC IEITER 89-21, "RDQUILT PCR 3/19/90 INFORRTION O'NCERNDG S'IATUS OF IMP 1DIENIATIO4 OF UNRESOLVID SAITTY ~ ISSUES (USI) REQUIREMENTS" l 74559 RELIEF RDQUEST ON MAIN S'IEAM ERAIN 12/14/89 VALVES, ASME SECTION XI. 74564 NJLIETIN 89-03, " POTENTIAL 106S OF 1/21/90 RDQUIRED SIRTTDCMN MARGIN IURDC REFUELDC OPERATIONS" 74577 F* EXTENSIQ4 2/23/90 74578 IDSS OF OFFSITE 10WER EVENT 7/11/89 2/21/90 74735 GENERIC IETTER 89-07, " POWER REACItR 1/22/90 SAFIGUARDS O2frDGINCY PIANNDC FOR SURFACE VEHICIE BCMBS". 74821 RENUMBERDC OF 3/4.7.11 2/12/90 74824 75 3/4.5.2 RDO.'AL OF RHR SYSTEN 3/6/90 AUIOCLOSURE DffERIOCK (ACI) 74825 15 3.8.1 & 3.8.2 DG FUEL OIL 6 2/12/90 VOIINE 74826 . TS TABI23 2.2-1 & 3.3-4, REPIACEMENT 3/15/90 OF RIDS FOR RID BYPASS MANIFDID 74839 TS 4.4.5.4 SG 'IUBE SIEEMES, B&W 3/22/90 75004 GENERIC IEPIER 89-19, "SAFETt 5/8/90 IMPIJCATIONS OF CONIBOL SYSTINS IN INR NUCIEAR ICWER PIANIS" 75049 is ON DEIETION OF CYCIE SPECIFIC 3/6/90 PARAMETERS 75061 RDQUAtlFICATIQ1 SGEDUIE 2/28/90

i s t Tpc5 m m m Ihg LQ. DESCRIPTICH OF 7HE TAC DNIT CIDSED 75359 TS 3/4.3.3.6, TABIES 3.3-10 AND 4.3.7, 2/12/90 REVRHR SUMP IN 75360 TS 4.7.15, MSIV FITOKE TIME TEST 5/17/90 75361 75 4.0.2, 3.25 SURVEILIANCE TIME LDET 2/12/90 75723 GDERIC IIITER 89-10, "SAITIY RELATED 6/11/90 p TrsrDC AND SURVEILIANOC" 75877 AMDOENT 70 INCINERATE CDfDMDATED OIL 5/17/90, 75953 RD20EST FOR APN%L 70 USE SB-166 3/5/90 i 76299 REIAXATION OF STAFF IOSITION IN GENERIC 10/5/90 ILTTER 83-28, ITD4 2-2, PARP 2 "VDEXR DTTERTACE IVR SATWrl-REIATED CCFJOHNTS", GDTERIC IEITER NO. 90-03. 76358 PMXW RDQUEST ON VALVE, XVG 8701 A&B 4/24/90 Items Wich have been closed out since the last licensing status meeting, i + e + 3 ., ~... -

ENCLOS'JRE 3 ENGINEERS SOricl239-02-7834 Engineer 6.G. W w l TECENICAL WORK RECORD Date 10/15/90 Project Title __PSV SET POINT TOLERANCE INCREASE Tab Page l of_1. South Carolina Electric & Gas Co. has submitted a Tech. Spec, change to increase the Pressurizer Safety Valve (PSV set point The following para) graphs show tolerance from +/- 1% to +/- 3%. that the Tech. Spec. margin of safety for the upper and of the PSV 3 tolerance has not been reduced. ) PLANT TECHNICAL BPECIFICATIONS - PSV's During normal operation, Tech. Spec. 3.4.2.2 currently requires that the PSV's be set at 2485 psig +/- 1%. A visit to the Bases for this particular Tech. Spec. indicates that the PSV's are required to operate to prevent the Reactor Coolant System (RCS) from exceeding its Safety Limit of 2735 psig. The Safety Limit of 2735 psig is given in Tech. Spec. 2.1.2. A visit to the Bases for this Tech. Spec. indicates that the Safety Limit is based on ASME B&PV Code Section III requirements. The ASME code : Squires that anticipated transient pressures cannot exceed 110% of design pressure. Since design pressure is 2485 psig (2500 psia) then 110% of design pressure is 2735 psig (2750 psia). Hence the Tech. Spec. Safety Limit is the same as that required by the ASME Code. The ASME Code margin of safety consists of the those pressures which exceed 110% of design pressure but are less than the pressure which causes ultimate failure of the pressure boundary. In this case, the ASME Code margin of safety and thus the real Tech. Spec. margin of safety is the area between 2735 psig and ultimate failure of the RCS pressure boundary. ASME B&PV CODE The ASME B&PV Code Section III ('71 ed., W'72 add.) under subsection NB-7411 requires that the " total rated relieving capacity shall,..., be suf ficient to prevent a rise in more than 10 per cent above system design pressure... pressure of under any pressure transients anticipated to arise" (Condition I II events). NB-7511 further requires that at least one safety valve be set at the system design pressure. NB-7512 requires that pressure drop including back pressure be considered in meeting the 110% of design pressure requirement. No mention is made of any requirement to consider any safety valve set point tolerance in the system design. NB-7614.3 requires that the safety valve itself shall have a popping-point tolerance of +/- 14. However, Section XI ('77 ed., S'78 add.) does not specify a set point tolerance. Verification Approval Type of Verification verifier signature /Date signature /Date

( \\ ENGINEERS Scricl239-02-7834 EngineerA& Mwaas TECHNICAL WORK RECORD Date 10/15/90 Project Title __PSV SET POINT TOLERANCE INCREASE Tab Page_.L o f,_2,, OM-1 specifies that the valves when tested shall not exceed their stamped set pressure by 3% or greater. The corresponding ASME B&PV Code Edition & Addenda for Section III subsection NB-7000 do not address the 3% tolerance. WESTINGHOUSE SAFETY ANALYSES The Westinghouse safety analyses for anticipated transients is bounded by the " Loss of Load / Turbine Trip 6100% Power" event for overpressurization events. Maximum system pressure attained with the PSV's set at +3% (2560 psig, 2575 psia is 2621 psig (2636 This is well below the 110% design pr) essure limit of 2735 psia). psig (2750 psia). In f act, if all three of the PSV's should be set at + 3% coincident with a + 3% drift on all three valves and a " Loss of Load / Turbine Trip 9 100% Power" event (an extremely unlikely event), RCS pressure would D.pt exceed the 2735 psig requirement.

However, it should be noted that the difference between the Westinchouse safety analyses and the Tech. Soec. Safety Limit i fesian marcin not Tech. Soec. marain.

t Condition IV events are events which are not anticiented to occur but are designed for because of their potential radiological consequences. These events are not addressed in the above mentioned Tech. Spec.'s nor their associated Bases. Design requirements are that the transient pressure not exceed 120% of the system design pressure. Since design pressure is 2485 psig (2500 psia) then 120% of design pressure is 2985 psig (3000 psia). The Westinghouse safety anaT,yws for condition IV events shows that the 120% of system design pressure requirement will not be exceeded. CONCLUSIONS The Tech. Spec. margin of safety remains unchanged for the increase of PSV set point tolerance from +/- 14 to +/- 3%. The Tech. Spec. requirements for PSV set point and the RCS Safety Limits are based upon the requirements of the ASME B&PV Code section III. Westinghouse safety analyses, in accordance with the ASME B&PV Code, have shown that anticipated transients coincident with an increased PSV set point tolerance (+3%) will not cause the RCS Safety Limits to be exceeded. The Tech. Spec. margin of safety is that above the safety Limit (the ASME limit of 110% design pressure) and below ultiteate f ailure. Thus the Tech. Spec. margin of safety remains unchanged. Verification Approval Type of verification verifier signature /Date Signature /Date -~v

ENCLOSURE 4 ,I- ^ ~ Vice Prr2.t. Nudear Operatens J. L Skolds I I l l General Manager, General Manager, General Manager, General Manager, General Manager, '~ Nudear Plant Station Support Engineering Services NuclearSafety Adnunistratsve and Support Serwnes Operations i l G. G. Soult D. R. Moore M. D. Quinton j K. W. Nettles M. B.Willianus j NudearTech. I Operations Education and Desegn Technical Fachties & Training Engineering Oversete Administrahon j Nudear Ops. Systems & - Maintenance Education and Performance Quality Budget & Services Training Engineering Systems Cost Control Planning and Core Eng. & Corporate Chemistry & Regulatory Nudear Nudear Health Physsa & Health Physics Support Computer Serv. Licenssng Env. Programs Nudear J Technical Protection Materials & Services Services Procurement Steam Generator Project

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-e PROPOSED TECHNICAL SPECIFICATION CHANGE REQUESTS Date: October 12.1940 ~ PROPOSED PRIORITY TAC # RTS# IM VP STATUS RIRC - RB System pH Chances to Bases B3/4 5-3. B3/4 64 T5P900007 EWR 10/31/90 BRC-ZIRLOTech Spec Change (L) T5P890021 EWR 11/06/90 MRC-MOV Thermal Overload Prot. & Bypass Devices TSP 870014 JDG 11/16/90 WRC-ESFAS/RT5 8nstrumentation - Reactor protettson T5P880025 ARR 11/16/90 System Tech. Spec. Change (H) MWG NQC-Implementation of Programmatec Controls for Rad. TSP 890004 MWG 11/16/90 Effluent T/5-ODCM or PCP (M) WRC-Training - T/5 5ettion 6 (M/H) T50900004 MWG 11/16/90 WRC - PSRC T/5 Change - Clanfecation Letter T5p900005 JDG 11/16/90 WRC - Main 51 cam Safety Valves - T/5 3.7.1.1 (L) T5P 880018 DCH 12/17/90 NRC-Segregation of D/G Load Test from Recuirements of TSP 890020 DCH 12/17/90 lategrated Safeguards Testing (T/5 4.81.1.2.E.7.D) (L) WRC -T/5 4 8 2.1 - Battery BarAs (M) TSP 900002 EWR 12/17/90 WRC - Shutdown Margins for inoperable Control Rods (L) TSP 870013 EWR 02/01/91 RRC-Remove Table 3.6.4 from T/5 (L) T5p880024 ARR 02/01/91 WRC - Accident Monitonng instr-Change Table T5P 890005 MWG 02/01/91 WRC-Change of Initial Containment Negative Pressure (L) T5P890010 EWR 02/01/91 MRC-Negative Rate Flua Trip Removal (L) TSP 890012 ARR 02/01/91 N RC - Increase $1 Response Time - Table 3.3-5 (L) T5P 890022 MWG 02/01/91 NRC-Admin T/5 Change to Make Table 3.3-10 Consistent TSP 900001 EWR 02/01/91 with A(teon Statement 3 3.3.6 (L) NOK-Steam Flow Measurement at Low Power Levels (L) TSP 900006 EWR 02/01/91

!r 0 DISTRIBUTION FOR MEETING

SUMMARY

DATED: October 30, 1990 Facility: Summer Socket M le 'NRC PDR ~ Local PDR T. Murley 12-G-18 F. Miraglia 12-G-18 E. Adensam 14-B-20 P. Anderson 14-B-20 - G. Wunder 14-B-20 DGC 15-B-18 E. Jordan MNBB-3302 L. Cohen G. Hsii

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