ML20246M924

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Summary of 890418 & 19 Meetings W/Region II & Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Handouts Encl
ML20246M924
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 05/08/1989
From: Hayes J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8905190299
Download: ML20246M924 (11)


Text

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May 8, 1989

. DISTRIBUTION l

iDocket File; ACRS(10)

NRC'PDR RBorchardt Local PDR PD21 r/f EAdensam PAnderson I JHayes {

Docket No. 50-395 OGC l Edordan(MNBB3302) l LICENSEE: South Carolina Electric & Gas Company BGrimes (9A2) l FCantrell FACILITY: V. C. Summer Nuclear Station, Unit No. I- PHopkins

'RPrevatte

SUBJECT:

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL On April 18 and 19, 1989, the NRC staff consisting of representatives of the Office of Nuclear Reactor Regulation, Region II and the Summer Resident Inspectors met with representatives of the South Carolina Electric & Gas Company (SCE&G) to discuss the status of the licensing issues for the V. C.

Summer Nuclear Station. The meeting was held at the Summer Station, Jenkinsville, South Carolina. A list of those persons who attended the meeting is included as Enclosure 1. I DISCUSSION On April 18, 1989, 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 1. The Summer project manager met with o of licensee's engineers to discuss the additional information required to evaluate the licensee's request for an extension of operating license to 40 years from the date of issuance of the operating license.

The next meeting is currently scheduled for June 1989, in the Region II offices in Atlanta, Georgia.

/s/

John J. Hayes, Jr., Project Manager Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

As stated CFff cc w/ enclosures:  ;

I See next page

[SUMMTG

SUMMARY

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Mr. 0. S. Bradham

-South Carolina- Electric & Gas Company Virgil C. -Summer Nuclear Station Cc:

Mr. William A. Williams, Jr. I Technical. Assistant - Nuclear Operations Santee Cooper

.P. O. Box.764 (Mail Code 153) 4 Columbia. South Carolina 29218

-J. B.~Knotts',-Jr., Esq. j Bishop, Cook, Purcell +

1 and Reynolds 1400 L Street, N.W. '

. Washington, D. C. 20005-3502 Resident Jnspector/ 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 Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P. O. Box 293 Winnsboro, South Carolina 29180 Attorney. General P. O. Box.11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600. Bull Street Columbia, South Carolina 29201 South Carolina 1.lectric & Gas Company Mr. A. R. Koon, Jr. , Manager Nuclear Licensing

-Virgi.1 C. Sumer Nuclear Station P. O. Box 88 3

Jenkinsville, South Carolina 29065

ENCLOSURE 1 ATTENDANCE APRIL 18, 1989 SCE&G NRC A. Koons, Jr. F. Cantrell J. Skolds J. Hayes, Jr.

P. Hopkins i R. Prevatte i

=l APRIL 19, 1989 a SCE8G NRC A. Monroe J. Hayes, Jr.

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ENCLOSURE 2

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STATUS OF NRC TACS FOR THE V. C. SUMMER PLANT April 10, 1989 i

49976 ISI PROGRAMS ISI (MARTIN :iUME)

-REVIEW REMAINS OPEN.

51287 SPDS (G. WEST)

-SER ISSUED

-THREE OPEN ITEMS

1. TOP LEVEL ICONICS ARE NOT CONTINU0USLY DISPLAYED.

2.

a. SYSTEM RESPONSE TO OPERATOR COMMANDS IS VERY SLOW. '
b. SYSTEM HAS NOT BEEN ABLE TO MEET ITS UNAVAILABILITY G0AL OF LESS THAN 1 %.
c. LACK OF REDUNDANCY IN THE DATA ACQUISITION CONTROLLER AND THE UNIBAR CONTROL SWITCH INCREASES THE VULNERABILITY OF THE SYSTEM TO FAILURES CAUSED BY THESE COMPONENTS.
3. HUMAN FACTOR PRINCIPALS NEED TO BE RESOLVED.
4. SOME NON-VALID VALUES OR CONDITIONAL FLAGS EXISTED FOR RHR FLOW RATE, SUBC00 LING MARGIN,(REACTOR VESSEL SYSTEM RVLIS),STARTUPRATE, LEVEL INDICATION CONTAINMENT HYDROGEN, AND SAFETY INJECTION (SI) FLOW.

-RESPONSE SENT FROM THE LICENSEE 6/16/88

-LICENSEE COMMITTED TO A NEW SPDS TO BE INSTALLED DURING 1990 REFUELING OUTAGE.

-WILL NECESSITATE NEW NRC REVIEW CYCLE.

-ANTICIPATED CLOSURE OF THIS ITEM IS 12/31/90.

-LETTER SENT TO SCE&G 11/22/88 INDICATING REVISED REVIEW SCHEDULE.

-LICENSEE PROVIDED A MILESTONE SCHEDULE FOR THE INSTALLATION OF THE SPDS ON 3/6/89.

51606 RV AND SV TESTING (II.D.1) (GARY HAMMER)

-SCE&G SUBMITTED RESPONSE TO STAFF COMMENTS ON i 5/9/88. l

-ADDITIONAL QUESTIONS SUPPLIED TO SCE&G AS A RESULT OF THEIR 5/9/88 RESPONSE.

Q W

-DRAFT 0F SCE&G RESPONSES TO NRC QUESTIONS GIVEN TO HAMMER ON 7/25/88. I

-CONFERENCE-CALL HELD ON THE RESPONSES 8/10/88. i

-SCE&G TRANSMITTED FOLLOWING INFORMATION IN DRAFT FORM-(1) DRAWING C-314-601 WENT TO EG&G, IDAHO 8/11/88; (2) ACCEPTANCE CRITERIA FOR NORMAL, EMERGENCY,'AND UPSET CONDITIONS ON 9/21/88 TO G. HAMMER;

o. (3) EXPLANATION OF DISCREPANCIES BETWEEN RESPONSES TO QUESTIONS 6 AND 9 AND FSAR TABLE 5.2.3 ON 9/21/88 TO G.

HAMMER.

-NRC PROVIDED COMMENTS ON RESPONSE TO ITEM B 0F SCE&G DRAFT RESPONSES.

-SCEAG OWES FORMAL SUBMITTAL.

53406 AUTO SHUNT TRIP TS, GL 83-28 ITEM 4.3 (DON LASHER)

-RAI ISSUED.

-CLARIFICATION

-THAT TS TABLE 4.3-1 FUNCTIONAL UNIT NO. 1

" MANUAL REACTOR TRIP" APPLIES TO RT BYPASS BREAKERS AS WELL AS RT BREAKERS. {

-TS TABLE 4.3-1 NOTATION 13 DOES NOT COMPLY WITH THE GL WHICH SPECIFIES AN AUTOMATIC UNDERV0LTAGE TRIP.

-RESPONSE RECEIVED FROM THE LICENCEE 1/20/89 .

i WITHDREW INITIAL AMENDMENT REQUEST AND PROPOSED NEW CHANGE TO THE TS CONSISTENT WITH GL 85-09.

-SH0LLY IN PREPARATION,

-SE INPREPARATION.

53720 ITEM 2.2 0F GL 83-28, EQUIP. CLASSIFICATION AND VENDOR INTERFACE FOR SAFETY RELATED COMPONENTS (DONLASHER)

-FARLEY TO BE HANDLED AS THE LEAD PLANT

-TER ISSUED BY EG&G

-0 PEN ITEMS ARE:

-CONTACT VENDORS OF KEY COMPONENTS SUCH AS AFW PUMPS, ECCS PUMPS SAFETY RELATED BATTERIES, AND SAFETY RELATED VALVES TO FACILITATE THE EXCHANGE OF CURRENT TECHNICAL INFORMATION.

AN INFORMAL INTERFACE AGREEMENT SHOULD BE ESTABLISHED.

-FOR DGs AND SAFETY RELATED SWITCHGEAR VENDORS A FORMAL INTERFACE SIMILAR TO THAT WITH THE NSSS SHOULD BE ESTABLISHED. I

-GENERIC LETTER TO BE ISSUED LATE SUMMER.

-GENERIC LETTER WILL PROVIDE GUIDANCE ON VENDOR INTERFACE, LICENSEE WILL BE REQUESTED TO CONFORM BY LETTER THAN THEY MEET GL, AND NRC MAY INSPECT LICENSEE'S PROGRAM.

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53942 ITEMS 4.2.3 & 4.2.4 0F GL 83-28, PREVENTIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS, LIFE TESTING & REPLACEMENT (A. TOLSTON)

-BULLETIN IS BEING PREPARED TO SEND TO CRGR.

54030 ITEMS 4.5.2 & 4.5.3 0F GL 83-28, REACTOR TRIP SYSTEM FUNCTIONAL TESTING, ALTERNATIVES & TEST INTERVALS (D. LASHER)

-4.5.2 COMPLETED.

-0WNER'S GROUP TO TRANSMIT PACKAGE 10/88.

-TRYING TO CLOSE OUT ON A GENERIC BASIS.

{

55344 PROCEDURES GENERATION PACKAGES (SUPPLEMENT 1, NUREG- 0737) (GEORGE LAPINSKY)

-DRAFT SE ISSUED 6/29/87.

-PROBLEMS IDENTIFIED INCLUDED:

1. PLANT SPECIFIC TECHNICAL GUIDELINES.
2. WRITERS GUIDE.
3. PROGRAM USED FOR VALIDATION OF E0Ps.
4. TRAINING PROGRAM FOR UPGRADED E0Ps.

-SCE&G WAS TO RESPOND TO THE STAFF COMMENTS WHEN l 1

FURTHER STAFF GUIDANCE IS PROVIDED (SEE BELOW)..

-NRC TO PERFORM INSPECTION OF 16 FACILITIES TO DETERMINE IF A DIFFERENT APPROACH IS NECESSARY IN THIS AREA.

-NUREG TO BE ISSUED 4/89 TO PROVIDE ADDITIONAL GUIDANCE ON PGPs.

-SEs TO BE WRITTEN ON EACH PLANT WITH PLANT SPECIFIC COMMENTS ON THE PGPs. LICENSEE IS TO INCORPORATE THE COMMENTS OR MAINTAIN A COPY OF THE JUSTIFICATION AS TO WHY THE COMMENTS WERE NOT INCORPORATED.

-SUMMER SE IN PREPARATION 1

56935 RCP TRIP CRITERIA, GL 83-10D (S. L. WU) i

-SE FROM REVIEWER TO PM SCHEDULED 4/89.

-WILL CLOSE THIS ITEM OUT GENERICALLY BY MAKING REFERENCE TO THE OWNERS GROUP APPROACH. LICENSEE WILL BE HELD RESPONSIBLE FOR IMPLEMENTING THAT PROGRAM.

59402 40 YEAR OL LIFE AMENDMENT I

-LICENSEE RESPONDED TO RAI 3/30/88.

-PM TO HOLD MEETING WITH THE LICENSEE 4/18-4/21 TO DISCUSS THE ADDITIONAL INFORMATION REQUIRED TO

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EVALUATE THE AMENDMENT REQUEST.

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, '59451 DIESEL CENERATORS TS (J. LAZEVNICK)

-REQUEST FOR ADDITIONAL INFORMATION SUBMITTED TO SCE&G 11/9/87.

-COMMENTS-0N 11/9/87 LETTER DEALT WITH TS 3/4.8.1.1 AND 4.8.1.2.

-kESPONSE TO RAI FROM LICENSEE 5/16/88.

-7/28/88 SUBMITTAL FROM SCE&G MODIFIED TS t.8.1.1.2.a.3 BY SPLITTING INTO 2 SEPARATE

f. SURVEILLANCE REQUIREMENTS.

-RE-SHOLLIED 8/25/88.

-CONFERENCE CALL HELD 9/14/88.

-SCE&G SUBMITTED REVISED TS RESPONSE 11/18/89.

-SE RECEIVED FROM TECHNICAL BRANCH 11/9/88.

-CONFERENCE CALL HELD 12/88. SCE&G TO PROVIDE A REVISED RESPONSE T0. DELETE THE WORDS "0R VERIFICATION" FROM TS 4.8.1.1.1-4.8.1.1.3.

-REVISED TS SENT 4/5/89.

-REQUEST TO BE RESHOLLIED.

-AMENDMENT IN PREPARATION.

62803 CONTAlhMENT STRUCTURAL INTEGRITY (C. P. TAN)

-LICENSEE RESPONSE SENT 3/17/88.

-NRC REVIEW TO BE COMPLETED 4/15/88.

-MEETING HELD 5/16/88 AND 9/14/88.

-SCEaG SUBMITTAL 0F 9/29/88 ADDRESSED PREVIOUS

-CONCERNS..

-AMENUMENT IN PREPARATION.

64821 RSB 5-1, NATURAL CIRCULATION TEST OF THE REACTOR j . COOLANT

-REACTOR SYSTEMS BRANCH TO REVIEW THIS ITEM.

65060 REMOVAL OF FIRE PROTECTION REQUIREMENTS FROM THE TS GL 86-10

-RE-SHOLLIED 2/24/88.

-AMENDMENT TO HAVE BEEN ISSUED 5/88.

-CONCURRENCE STOPPED DUE TO FORTHCOMING GUIDANCE IN GENERIC LETTER TO DE ISSUED.

-GEhERIC LETTER ISSUED 8/3/88.

-MEETING HELD 8/17/88 TO DISCUSS REVISED SUBMITTAL AND GENERIC LETTER.

-LICENSEE SUBMITTED ADDITIONAL INFORMATION 1/31/89.

-AMENDMENT IN PREPARATION.

65778 REMOVAL OF ORGANIZATIONAL CHARTS FROM THE TS

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-SCE&G PROVIDED RESPONSE BASED UPON GL 88-06 ON 5/16/88..

-RE-SH0LLIED 8/25/88. I

-SUBMITTAL RECEIVED FROM SCE&G 12/22/88.

-AMENDMENT IN PREPARATION.

)

67340 ORGANIZATIONAL CHARTS TO REFLECT 1/25/88 RE0 ORGANIZATION 4

-SUBMITTAL RECEIVED FROM SCE&G 12/22/88.

-AMENDMENT IN PREPARATION.

67812 ISI RELIEF, HYDR 0 STATIC TESTING 0F THE SGB SYSTEM (M. HUME)

-RELIEF SE IN PREPARATION.

68045 SINGLE CELL CHARGING OF SAFETY RELATED BATTERIES (A. TOLSTON) ,

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-QUESTIONS ISSUED TO THE LICENSEE 6/27/88.

-RESPONSES RECEIVED 8/29/88.

-TECHNICAL GROUP PROVIDED SE 12/15/88.

-RESPONSE SENT TO REGION II CLOSING OUT THIS ITEM.

68046 IST 12/23/87 PROGRAM REVISION (K. DEMPSEY)

-SER ISSUED 4/19/88

-SOME RELIEFS DENIED, SOME GRANTED

-LICENSEE MUST ADDRESS APPENDIX C 0F THE TER WHICH C0 VERS OMISSIONS AND INCONSISTENCIES IN THE PROGRAM.

-MEETING HELD 6/1/88 TO DISCUSS RELIEFS WHICH WERE DENIED AND 12/23/87 REVISED PROGRAM.

-REVISED PROGRAM SUBMITTED BY SCE&G 8/31/88.

-TER TO BE ISSUED BY EG&G, IDAHO.

68610 IMPLEMENTATION OF STATION BLACK 0UT RULE, 10 CFR 50.63, A-22 (A.  ;

GILL)

-RESPONSE DUE 4/17/89 68834 BULLETIN 88-05, NON-CONFORMING MATERIALS SUPPLIED BY PIPING SUPPLIES, INC. AT FOLSOM, N.J. AND WEST JERSEY MANUFACTURING C0. AT WILLIAMST0WN, N. J., B-104.

-RESPONSE SUBMITTED 9/13/88.

-WRITTEN RESPONSE DUE 60 DAYS AFTER COMPLETION OF ALL SCHEDULED ACTIONS.

-INSPECTION CONDUCTED BY SCE&G 10/88.

-LICENSEE SENT LETTER ON RESULTS OF INSPECTION OF

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N0ZZLE PLATES ON 3/6/89.

69066 STEAM GENERATOR, L*.(H. CONRAD)

-ENVIRONMENTAL ASSESSMENT PUBLISHED IN THE FEDERAL REGISTER 10/88.

-CONFERENCE CALL HELD 10/25/88.

-PRELIMINARY REVIEW INtICATES THAT ADDITIONAL INFORMATION IS REQUIREL

-TECHNICAL STAFF REVIEW 70 BEGIN UPON FECEIPT OF ADDITIONAL SCE&G INFORMAi.'ON.

i 69693 BULLETIN 88-08, " THERMAL STRESSES IN PIPING CONNECTED TO REACTOR C0OLANT SYSTEMS

-RESPONSE SUBMITTED 9/29/88.

-MEETING HELD 10/6/88.

-ADDITIONAL INFORMATION SUBMITTED BY SCE&G  !

12/19/88.

-DIFFERENTIAL TEMPERATURE DATA SUBMITTED ON 3/23/89.

-PM TO CLOSE OUT.

69782 GENERIC LETTER 88-17. " LOSS OF DECAY HEAT REMOVAL" l

-RESPONSE TO EXPEDITIOUS ACTIONS PROVIDED-BY SCE&G 1/23/89.

-RESPONSE TO 6 PROGRAM ENHANCEMENTS PROVIDED BY LICENSEE 2/2/89. {

l 69978 BULLETIN 88-04, P0TENTIAL SAFETY RELATED PUMP LOSS. I

-WRITTEN RESPONSE DATED 7/8/88.

-VENDOR INFORMATION NEEDED ON EFW PUMPS MINIMUM FLOW REQUIREMENTS TO PREVENT DEGRADATION FROM HYDRAULIC INSTABILITY WAS DUE 8/88.

-WRITTEN RESPONSE DUE WITHIN 30 DAYS OF COMPLETION OF THE LONG TERM RESOLUTION ACTIONS.

-RESPONSE ON EFW PUMPS PROVIDFD 12/20/88.

-RESPONSE REQUIRED ON WHETHER INSTALLED MINIFLOW CAPACITY IS ADEQUATE FOR SINGLE PUMP OPERATION.

INFORMATION TO BE PROVIDED FOLLOWING 1990 REFUELING OUTAGE.

71360 NRC BULLETIN 88-10, "NON-CONFORMING M0LDED-CASED CIRCUIT BREAKERS".

-LETTER SENT TO SCE&G REQUESTING THAT INFORMATION BE PROVIDED AS IT BECOMES AVAILABLE.

-RESPONSE DUE NO LATER THAN 4/1/89.

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71554 GENERIC LETTER 88-11. "NRC POSITION ON RADIATION EMBRITTLEMENT OF REACTOR VESSEL MATERIAL AND ITS IMPACT ON PLANT OPERATIONS.

-RESPONSE SENT BY SCE&G 1/12/89.

-PM CLOSED OUT ITEM IN LETTER 2/7/89.

i 71725 GENERIC LETTER 88-14, " INSTRUMENT AIR SUPPLY SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT" l l

-RESPONSE SENT 2/2/89.

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

-PERIODIC DEWPOINT MONITORING AND SYSTEM BLOWDOWN AT SELECTED LOCATIONS INITIATED BY 8/1/89.

-FULL IMPLEMENTATION OF A QUALITY RELATED PROGRAM FOR DIAPHRAGMS BY THE FIFTH REFUELING OUTAGE (4/90).

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

72171 NRC BULLETIN 88-11, " PRESSURIZER SURGE LINE THERMAL STRATIFICATION"

-LICENSEE RESPONDED 3/1/89.  ;

-SUBMITTED RESPONSE TO 1.A 0F BULLETIN.

-LICENSEE INTENDS TO WORK WITHIN WOG.

-ALTERNATE SCHEDULE PROPOSED FOR 1.B 0F BULLETIN.

72727 AMENDMENT ON DC SOURCES (TS 3/4.8.2)

-APPLICATION SENT 8/24/88.

-SH0LLY IN PREPARATION.

-AMENDMENT IN PREPARATION.

72893 FEEDWATER ISOLATION VALVES (TS 3.7.1.6)

-REQUEST SUBMITTED 4/5/89.

-SH0LLY IN PREPARATION.

????? BULLETIN 88-03, INADEQUATE LATCH ENGAGEMENT IN HFA TYPE LATCHING RELAYS MANUFACTURED BY GE.

-RESPONSE SENT BY SCE&G 1/13/89

-PM CLOSED OUT 2/6/89.

????? BULLETIN 87-02, SUPPLEMENT 1, " FASTENERS TESTING TO

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DETERMINE CONFORMANCE APPLICABLE MATERIAL SPECIFICATIONS"

-RESPONSE SUBMITTED 7/20/88.

????? GENERIC LETTER 88-20, "INDIVIOUAL PLANT EXAMINATION FOR SEVERE ACCIDENT VULNERABILITY".

TACS CLOSED

' TAC NO. DESCRIPTION OF THE TAC DATE CLOSED 66258 LOSS OF RHR WHILE RCS PARTIALLY FILLED, 10/17/88 1/2 LOOP OPERATION.

c 67327 RAPIDLY PROPAGATING FATIGUE CRACKS IN 11/10/88 SG TUBES, BULLETIN 88-02.

67811 VANTAGE 5 FUEL, SPENT FUEL STORAGE. 10/28/88 68274 SG TUBE SLEEVING. 11/10/88 68644 VANTAGE 5 FUEL, REMAINING TS SECTIONS. 10/28/88 68956 BORIC ACID CORROSION OF C-STEEL 10/6/88 COMPONENTS IN PWR PLANTS GL 88-05.

????? BULLETIN 88-09, " THIMBLE TUBE THINNING 1/4/89 IN WESTINGHOUSE REACTORS".

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