ML20210K066

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Summary of 860321 Meeting W/Util in Bethesda,Md Re Status of Licensing Actions.List of Attendees & Submitted & Proposed Licensing Actions Encl
ML20210K066
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/31/1986
From: Hopkins J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8604040637
Download: ML20210K066 (8)


Text

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March 31, 1986 Docket No. 50-395 DISTRIBUTION ,

Docket File ."J. Hopkins NRC PDR~~ '0 ELD Local PDR E. Jordan LICENSEE: South Carolina Electric & Gas Company PAD #2 Rdg B. Grimes J. Partlow ACRS (10)

FACILITY: V. C. Summer Nuclear Station L. Rubenstein NRC Participants

SUBJECT:

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL On March 21, 1986, the NRC staff met with the South Carolina Electric and Gas Company (SCE&G) to discuss the status of licensing actions for the V. C.

Summer Nuclear Station. The meeting was held in Bethesda, MD. A list of those persons who attended the meeting is included as enclosure 1.

DISCUSSION A list (enclosure 2) of submiti.ad and proposed licensing actions was discussed with regard to the relative prioiity of the licensing actions for this calendar year. It was agreed that AC sources, steam generators, pressure-temperature limits, containment structural integrity, and 40 year 0.L.

extension are of higher priority than other actions.

fS Jon B. Hopkins, Project Manager PWR Project Directorate #2 Division of PWR Licensing-A

Enclosures:

As stated cc: Sea next page t

. AD#2

/M: PAD #2 b' JHopkins:he LRub9 nstein 3p/86 3/6/86 1

8604040637 960331 PDR ADOCM 05000395 P PDR

Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 167)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.

Washington, D. C. 20036 Mr. Mark B. Whitaker, Jr.

! Group Manager - Regulatory and Support Services South Carolina Electric & Gas Company P.O. Box 764 (Mail Code 160) 1 Columbia, South Carolina 29218 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 29180 ,

Attorney General Box 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health i South Carolina Cepartment of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201

B Enclosure 1 NRC SCE8G L. Rubenstein J. Connelly J. Hopkins A. Paglia l

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ENCLOSURE 2 1.IGNSING 11!9tS STAIUS LIST Sheet I cf 5 .

V. C. SIMER NUCIEAR STATIOi Date: Rarch 17,1986 TE09I1 CAL SPECIFICATIGI REVISIGIS SIDfITITD 10 NRR

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11DtlICAL fL981TTAL HDERAL RIEISTER NRR NRR SGEG S*ECIFICATImi TrIIF IEVISEN/PROBUM IR1E (S) ISSWEE 1EONICM, REVIEW APPIGAL IEQUIRED DATE DATE 3/4.8 "Ac Smrces" Revises the Tectnical Specification to 06-10-85 07-17-85 reduce the ntsiber and severity of starts 12-06-85 Exp. 08-16-85 of the diesel gmerators tiereby decreasing mgine wear and increasing reliability.

3/4.4.5 'stema Revises the Tecinical specificatim to .01-16-1E Generators" allow continued operation without plugging for tube sheet region tube defects (P*).

6.5.3.1.e '1 Qualified Need to correct reference to Section 4.4 08-02-85 Reviewer of Afst lo.1, 1971 Qualifications" 3/4.8.4 ' Electrical Revision replaced T.S. Tele 3.8.1, 04-29-85 Ewipment 'tetairument Penetration Cmductor 06-10-85 Protective Overcurrent Protective Device Test Setroint Devices" Criteria" with words to indicate which devices are required to be operable.

3/4.4.5 'Stese Revises the Tecletical Specification to 01-16-86 Cenerators" allow repair of the tubes as mi alternative 03-1fHl6 ta plugging (T4e Sleeving).

3/4.4.9 ' Pressure Revises tm witidrausl schedule for the 11-08-85 T w rature Reactor vessel Specification capsule. 02-07-86 I.imits" 3.5.3 'ECCS Subsystne Clarify valre aligrunmt requirenent for 03-17-86 Aligument" 155t in Mode 4.

' e-6.2.2.F ' Unit Staff . Clarify requirements for review of overtim 0}-17-86 e, Orertime" during exteded stutdout periods (see NRC interpretation.)

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Sheet 2 ef 5 ~

LI NSING ISSIES SIA1US LIST Dats Narch IV,19%

V. C. StMER NUaEAR STATION 1EOMICAL SPECIFICATION REVISIGE 1D BE SUIMITIED 2fD QQUt1ER 19%

1EONICAL SUtenTrAL RDERAL'KECISTER NKR NRR SONC SIECIFICATIGI TITIE IEVISIGI/IH0tUM DATE (S) ISSW12 1EONICAL REVIEW APPIUWRL IH}UIRED DATE DA1E 3.5.1.1 "A.C. Sources" Evaluate addressing Lost Sequencer in a separate specification. '

3.1.9.1 ' Tire Sgpressics, Evaluate Renoving all Fire Protectim Systen" from Tech. Spm. a=1 address in separate 3.7.9.2 " Spray aml/or doctsment (FSAR). ,

Sprinkler Systens' 3.7.9.3 '002 Systen" 3.7.9.4 ' Tire Hose Station" 3.7.9.5 " Yard Fire (

Hydraits ami h .

Stations" 3.7.10 ' Tire Rated Assablies" 3.3.1 w: Need to revise Spec. to implesment Instrismentatim" Westinghmae Omers Group optimization Prcgram.

3.7.1.2 'YJuergency Evaluate relaxing the monthly required Fentwater Systan' page flow test to a quarterly frequency consistent with ISI program.

3.7.1.6 "Feedwater Evaluate scope of Tech. Spec. to includa Isolatim other Feedwater Isolatim equig eit Valves" (i.e., Cmtrol Valves, Cmtrol Bypass Valves, ami Feedpaps) required for feeduster isolatim.

3/4. 5.4, 'Defueling Water Make abninistrative changes, as necessary.

Storage Tm*",

Tables 4.3-f 'Ef f luent '

mi 4.3-9 Mmitoring Instrunentat ion,'

Table 4.3-2 'ESF Actuation -

Systne Inststmarntaticii" ,, .-

3.4.8 " Specific Revise Tech Spec. in accordance with Activity" reccureviations in Generic Istter 85-19 to delete etenulative oprating limit on spn ific activity. l e

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Sheet 3 of 5 LIONSING ISSIES STATI!S LIST Date: March 17,1986 V. C. SlMER NtK1 EAR STATIOl UX1NICAL SITEIFICATION REVISIDE Y) BE SUIMITIED 3RD QtWIIER 1986 1B09I1 CAL S3IMITTAL FFDDIAL RfCISIER NRR NRR SOEC SfECIFICATIGi TTI1E IEVISitN/PR0t41M IM1E (S) ISSIAN 1EONICAL REVIEW AP190 VAL IEQtIIRFI)

DATE IM1E 3.7.3 'tcupment these Actim Statenents require going to Cooling Water cold stutdom wtum one train is lost, Systen" whm these systans are nenlai for 3.7.4 " Service Water cookicam.

Systen" 3.8.1.1 "A. C. Sources" l 3.3.3.5 '1tenote Slutacne Ation Statements require plait stutdom Instrianentat im" in specified time frames whm indication is lost. Nest to evaluate relaxing these ktim Statements to alls alternate ways of amitoring inoperable paraneter.

3.3.3.6 "kcident ktion Statantets requi.e plait stastdom Mmitoring in specified time frastas whm .ndicatim Instrumentatim" is lost. Nest to evaluate relaxing these ktim Statements to allow altemate ways of monitoring inoperable parameter.

3.1.3.2 '?osit ion ktion Statement is restrictive in that Irmlication it addresses our rod positim indicator Systens" being inoperAle when the IIX) requirement is on the systen level (i.e., Rcd positior indicatim systen arti denewi position indication systen).

3.4.6.2 '1K:S Operatimal Evaluate relaxing RCS Pressure Isolation

[ Ie dage" Valve leAage requirenent and/or evaluate deletion of same valves frtun Tale 3.4-1.

I ~3.6.4 't ontausurnt . A probles exists for past IMt testing of Isolat ion -

an ancperable ecntairveent isolation valve "*'

Valves" when that valve is the only emtairunent isolation.

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l l LIONSING ISSLES STAlUS LIST Sheet 4 of 5

, V. C. SOGER NUCIf.AR STATIOi Data: March 17,19%

11D9fICAL SIECIFICATION RFVISIONS 10 FE SU!PtITITD 41H QUAlf!ER 1986 1

l 11D91ICAL SU!PIITTAL FEDDtAL REEISIER NRR NRR SO%C l SffEIFICATION TillE EVISICN/PR06tRt IMIE (S) IS9]ANCE 1ECltilCAL REVIEW APPHOVAL IEQUIRED l DA1E IR1E l

l 3. 7.1.2 'Faergency III) requiressent is for oper41e pumps ard Redwater Systan' flow pathsI hoever, Action Statenent mly addresses ptsip(s) being ingerele.

Neal to exlify Action Statenent to aldress inoperable flow paths.

3.1.2.6 hatal Water III) has a 100 ppe range for Borm Sources Operatiny cmcentrat ion. Need to investigate 3.5.4 Refueling Water boardening this rage.

Storage Taa" klim Statment is very restrictive in W 1 3.3-3 " Automatic that it requires pimt sluitdown Itess 8 Stitchocer to if awe the one chenel is lost. Need l

Ocutairment Sm'I to sunlify Actim Statement to allow for j operator action.

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! 3.4.5 "Stema 4.4.5.3.C.3 requires miditional

Generator" mscheduled ISI if there is a II1CA l requiring ESF actim. This needs to be l clarified to better describe when an ISI is needed mesequret to this event.

314.}-1 'iteactor Trip Tecleical Specificatim to be revised System to optimize reactor trip breder testing.

Surveillance i Requirseents" 3.3.2 'ESF Need to revise Spec. to implene.it

  • Instnamentatim"*

Westinghouse f%ers Crmp optimizatim

. . programs. .. e- -

3.1 1.6 'tstairsent Surveillece equirements need revision Stnac tural 'assai m results of infomatim obtaine!

Integrity" during the first 3 surveillmce intervals.

Essentially a couplete rewrite of the surveillance Section will be proposed.

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Sheet 5 if 5' ,'

Li NSING ISSIES STA1US LIST Data: Rarch 17,1986 V. C. SIMER NtHEEt STATIOf ODER 1E0011 CAL IEVIIMS t ESTDR1TD ACIUAL SUIMITTAL ITEGIAL REGISTER NRR NRR SOEG RIQUIRfD I

11191 DESCRIPTION SUIMITTAL In1E (S) IS114N 1E0911 CAL APlil0URL ME tu1E REVIEW DA1E 40 Year 0.L Extmis 0.1 to 40 years fra date of 08-02-85 immunice 1.icense Extends operatim of microseimnic 03-29-85 Ccsuiitim smitering r.etwork irviefinitely 01-09-86 l 2.C (24)

! It.k.3.31 RIIKI1CA NUREC 0737 - 05-21-86 Ccmfirmatory Analysis Cetrol Roan OeR Finst Report sutunitted I.-15-85. 2:=1 Q.

l Design kspmee to questicns received fra NIC

! Review 06-21-85.

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l IS! Prcurm Relief request to revise limits 2nd Q.

Revicim for pimp DP auf flee to acemnt for l

instnmentation sul meter resting l AnacCutacles.

l 0737, Itesa Respmse to NIC Staff questims (letter 3rd Q.

l II.D.1 dated 7-11-85) pertaining to relief and i t safety valves. 1hese gestions are in l

cmjisictim with IRufC 0737. Iten II.D.I. -

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