ML20245J211
| ML20245J211 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/28/1989 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8903060202 | |
| Download: ML20245J211 (15) | |
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February 28,1989e E ,(Docket _No.L50-395i -
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LICENSEE:~ South. Carolina Electric & Gas-Company.- .j FACILITYL V.iC. Summer . Nuclear ~ Station, Unit ~ No.1 3
SUBJECTL: SUlHARY OF MEETING WITH SOUTH CAROLINA: ELECTRIC a GAS ~ COMPANY g -GENERAL' ,.
On-February 7, 1989,ithe NRC staff consisting of' representatives of the Office-
.of' Nuclear Reactor Regulation,:and the Summer Resident Inspector met with= <
representatives of the South Carolina Electric & Gas' Company (SCE&G)ito discuss
~
< the status of the licensing issues for the V.' C. Summer _ Nuclear Station. :The meeting was Lheld,at' the_ NRR Office. in?Rockville, Maryland. A list 20fithose
- persons who attended the meeting is. iricluded,as Enclosure 1. . .
,+ , 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. During:the meeting the licensee lprovidedia listing.
of amendment. requested submitted and 1those'under s consideration for submittal.
This,is' included:as: Enclosure 3.- t '
The next meeting-_is currently scheduled for April 1989, in.the Region.II
' offices:in. Atlanta, Georgia.; -
/5/
John 'J. Hayes, Jr., Project Manager Project Directorate 411-1 Division _of Reactor Projects.I/II-2 0ffice of Nuclear Reactor Regulation
Enclosures:
As stated-cc.w/ enclosures:
-See-next page
[ SUM _.MEETING
SUMMARY
]
/
OFC; eP LDRPR:D: 2h:5RPR : : : : : :
_____:_ . ___:.. rp. . . : . . . . . . . _ _ _ _ : . . _ _ _ _ _ _ . . . : _ _ _ _ _ _ _ _ _ _ _ : - _ _ _ _ _ _ _ _ _ _ _ : _ . . _
LNAME':JH s jfw ':ER es : : : : :
..__.:____7.._____:___ ________:_. ___...___:____________: ___________:_-________--:___..______
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DATE:2/2F89' -- i 2/ ny
/89 : : : : :
0FFICIAL: RECORD COPY k
8903060202 890228 N\
PDR ADOCK 05000395
_l___________ _ _ _ _ _ . _ PDC
i x.
- Mr. O. S.: Bradham : -
p South Carolina Electric & Gas, Company- Virgil C. Summer Nuclear Station-L.
I . cc:.
Mr.' William A. Williams, Jr.
Technical Assistant.~- Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)
Columbia, South Carolina : 29218
-J.'B. Knotts, Jr., Esq.
81 shop Cook,:Purcell.
and Reynolds 1400 L Street, N.W.
Washington, D. C. -20005-3502 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 South Carolina Department'of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201
-South Carolina Electric & Gas Company Mr. ' A. R. Koon, Jr. , Manager Nuclear Licensing Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065 i
., . s : _ .. ,.
~
3.. .
.,< :1 p; < g; n ENCLOSURE 1- .l ATTENDANCES FEBROARY 7, 1989 ,
- .7,
' SCE&G :
__ NRC.
.W.-;Higgins-J .' . Hayes -
A. Koon, Jr.-
P. Hopkins 5
1
, l 1
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7;
. . ~ ENCLOSURE'2
. 1 STATUS OF NRC TACS FOR THE V. C.-SUMMER PLANT-
, February 7, 1989-49976 ISI PROGRAMS ISI-(MARTIN HUME) 1
-REVIEWER PROMISED SE BY 6/88.
-ITEM NOW GIVEN LOW PRIORITY.
-PM TO INVESTIGATE WRITING SE HIMSELF.
51287 SPDS (G. WEST)
-SER ISSUED
-THREE OPEN ITEMS ~
I. TOP LEVEL ICONICS ARE NOT CONTINUOUSLY-DISPLAYED. 4
?
- 2. -
- a. SYSTEM RESPONSE TO OPERATOR COMMANDS IS VERY SLOW.
4
.~b. SYSTEM HAS NOT'BEEN ABLE TO MEET ITS. -
UNAVAILABILITY G0AL OF LESS THAN 1 5. ;
- 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 LEVEL INDICATION SYSTEM (RVLIS), STARTUP RATE, 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. l
-ANTICIPATED CLOSURE OF THIS ITEM IS 12/31/90. )
-LETTER SENT TO SCE&G 11/22/88 INDICATING l REVISED REVIEW SCHEDULE.
51606 RV AND SV TESTING (II.D.1) (GARY HAMMER) '
-SCE8G SUBMITTED RESPONSE TO STAFF COMMENTS ON 5/9/88.
I l
L 1. 7 - -
-ADDITIONAL QUESTIONS SUPPLIED TO SCE&G_AS'A RESULT '
OF THEIR 5/9/88' RESPONSE. E
-DRAFT OF SCEAG RESPONSES TO NRC QUESTIONS-GIVEN T0-HAMMER ON 7/25/88.. 1
-CONFERENCE CALL' HELD ON'THE RESPONSES 8/10/88. l
-SCEAG TRANSMITTED FOLLOWING INFORMATION-IN DRAFT ~ d FORM:
(1) DRAWING C-314-601.WENT1TO EG&G, IDAHO.
8/11/88; -
(2) _ ACCEPTANCE CRITERIA FOR NORMAL, .
a
. EMERGENCY, AND UPSET CONDITIONS ON 9/21/88 TO G. HAMMER; (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 B0FSCEAGDRAFTRESPONSES.y-SCE8GWILLPROVIDE )
==- FORMAL SUBMITTAL.
-SE T-0 BE ISSUED . '!
(
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. I
" MANUAL REACTOR TRIP" APPLIES TO RT BYPASS
-BREAKERS AS WELL.AS RT BREAKERS.
-TS~ TABLE 4.3-11 NOTATION 13 DOES NOT COMPLY WITH THE GL WHICH SPECIFIES AN AUTOMATIC.
UNDERVOLTAGE TRIP.
-RESPONSE RECEIVED:FROM THE LICENSEE 1/20/89 WITHDREW INITIAL AMENDMENT REQUEST AND PROPOSED NEW CHANGE TO THE~TS CONSISTENT WITH GL 85-09.
53720 ITEM 2.2 0F GL 83-28. EQUIP. CLASSIFICATION AND VENDOR INTERFACE FOR SAFETY RELATED COMPONENTS (DON LASHER)
-FARLEY TO BE HANDLED AS THE LEAD PLANT
-TER ISSUED BY EGAG
-OPEN ITEMS ARE: '
-CONTACT-VENDORS OF KEY COMPONENTS SUCH AS AFW PUMPS, ECCS PUMPS SAFETY RELATED BATTERIES, ;
AND SAFETY RELATED VALVES T0-FACILITATE THE l EXCHANGE OF CURRENT TECHNICAL INFORMATION.
e 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.
-PM TO INVESTIGATE WRITING SE HIMSELF.
.., s 7*:
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 BY 6/89.
ITEMS 4.5.2 & 4.5.3 0F'GL 83-28 54030 REACTOR TRIP SYSTEM FUNCTIONAL TESTING, ALTERNATIVES & TEST INTERVALS (D. LASHER)
-4.5.2 COMPLETED.
-0WNER'S GROUP TO TRANSMIT PACKAGE 10/88.
-TRYING T0 CLOSE OUT ON A GENERIC' BASIS.
-RESOLUTION EXPECTED'4/89.
55344 PROCEDURES GENERATION PACKAGES '
NUREG- 0737) (GEORGE LAPINSKY) (SUPPLEMENT 1, .
-DRAFT SE ISSUED 6/29/87.
-PROBLEMS IDENTIFIED INCLUDED:
- 1. PLANT SPECIFIC TECHNICAL GUIDELINES.
- 2. WRITERS GUIDE. 2
- 3. PROGRAM.USED FOR VALIDATION OF EOPs.
- 4. TRAINING PROGRAM FOR UPGRADED E0Ps.
-SCE&G WAS TO RESPOND TO THE STAFF COMMENTS WHEW FURTHER STAFF GUIDANCE IS PROVIDED (SEE BELOW)..
-NRC TO PERFORM INSPECTION 0F 16 FACILITIES TO DETERMINE IF A DIFFERENT APPROACH IS NECESSARY IN THIS AREA.
-NUREG/CR T0-BE ISSUED 3/89 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. l l
56935 RCP TRIP CRITERIA, GL 83-10D (S. L. WU)
-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
-LICECSEE RESPONDED TO RAI 3/30/88.
L
f.. ,
4 Q' j g*f~
i
(?
-ITEM NAS THE LOWEST OF PRIORITIES (4)'. . J"
, -WILL: EVALUATE' PM PERFORMING- THE REVIEW.
59451- DIESEL GENERATORS TS (J.: LAZEVNICK)'
-REQUEST-FOR ADDITIONAL INFORMATION SUBMITTED _TO SCE&G 11/9/87.-
-COMMENTS ON 11/9/87 LETTER DEALT WITH-TS 3/4.8.1.1' AND 4.8.1.2.
-RESPONSE TO RAI FROM LICENSEE:5/16/88.
-7/28/88' SUBMITTAL FROM SCE&G MODIFIED TS .
'4.8.1.1.2.a.3 81 4PLITTING : INT 0 ' 2 . SEPARATE SURVEILLANCE REqr.iREMENTS.
-RE-SHOLLIED 8/25/88.
-CONFERENCE-CALL 6'LD 9/14/88.-
-SCEAG SL7MITTEb 6: VISED TS RESPONSE 11/18/89.
-SE RECEIVED FR0h' TECHNICAL BRANCH 11/9/88.
-CONFERENCE CALL HELD 12/88. SCE&G.TO PROVIDE _Av REVISED RESPONSE TO DELETS THE WORDS "0R VERIFICATION" FROM TS- 4.8.1.1.1-4.8.1.1.3..
I 62803 CONTAINMENT 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..
-SE RECEIVED FROM TECHNICAL BRANCH 12/19/89.
-SE TO BE ISSUED 2/89.
64821 .RSB 5-1, NATURAL CIRCULATION TEST OF THE REACTOR COOLANT
-REACTOR SYSTEMS BRANCH TO REVIEW THIS ITEM. -SE TO BE ISSUED BY TECHNICAL BRANCH 4/89.
65060 REMOVAL OF FIRE PROTECTION REQUIREMENTS FROM THE TS GL 86-10 l -RE-SHOLLIED 2/24/88.
L -AMENDMENT TO HAVE BEEN ISSUED 5/88.
-CONCURRENCE STOPPED DUE TO FORTHCOMING GUIDANCE IN GENCRIC LETTER TO BE ISSUED.
-GENERIC LETTER ISSUED 8/3/88.
-MEETING HELD 8/17/88 TO DISCUSS REVISED SUBMITTAL AND GENERIC LETTER.
-LICENSEE TO SUBMIT REVISED AMENDMENT REQUEST DURING THE WEEK OF 1/30/89.
L_-__ -_-_ _.
9
. j 1
65778 REMOVAL OF ORGANIZATIONAL' CHARTS FROM THE TS
-SCE8G PROVIDED RESPONSE BASED UPON GL 88-06
-R - H0 L b'8/25/88. '
-SUBMITTAL RECEIVED FROM SCE&G 12/22/88.
-SE TO BE ISSUED 2/89. <j 1
67340 ORGANIZATIONAL CHARTS TO REFLECT 1/25/88 REORGANIZATION
-SUBMITTAL RECEIVED FROM SCE&G 12/22/88.
-SE TO BE ISSUED 2/89.
67812 ISI REL'IEF, HYDROSTATIC TESTING OF THE SGB SYSTEN (M. HUME) .
-SE T0-BE ISSUED BY PM 2/89.
68045 SINGLECELLCHARGINGOFSAFETYRELATEDBATTERIESh.
(A. TOLSTON)
-QUESTIONS ISSUED TO THE LICENSEE 6/27/88.
-RESPONSES RECEIVED 8/29/88.
-TECHNICAL GROUP PROVIDED SE 12/15/88.
-TECHNICAL GROUP OWES REGION II INFORMATION.
68046 IST 12/23/87 PROGRAM REVISION (K. DEMPSEY)
-SER ISSUED 4/19/88
-SOME RELIEFS DENIED, SOME GRANTED
-LICENSEE MUST ADDRESS APPENDIX C OF THE TER WHICH COVERS OMISSIONS AND INCONSISTENCIES IN THE PROGRAM. l
-MEETING HELD 6/1/88 TO DISCUSS RELIEFS WHICH WERE' t DENIED AND 12/23/87 REVISED PROGRAM.
-REVISED PROGRAM SUBMITTED BY SCE&G 8/31/88. i
-TER TO BE ISSUED BY EG&G, IDAHO APPR0XIMATELY 1 3/89.
68610 IMPLEMENTATION OF STATION BLACK 0UT RULE, 10 CFR ;
50.63, A-22 (A. GILL) !
-RESPONSE DUE 4/17/89
,,. eg ' e 68834. BULLETIN 88-05, NON-CONFORMING MATERIALS SUPPLIED- '
BY. PIPING 1 SUPPLIES, INC. AT FOLSOM, N.J. AND WEST
' JERSEY MANUFACTURING CO. AT WILLIAMSTOWN N. J.,
o 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.
-RESPONSE OWED 12/88.
69066 STEAM GENERATOR, L* (H. CONRAD) 4 -ENVIRONMENTAL ASSESSMENT PUBLISHED IN THE FEDERAL.
REGISTER 10/88.
-CONFERENCE CALL HELD 10/25/88.
-PRELIMINARY REVIEW INDICATES THAT ADDITIONAL ~
INFORMATION IS REQUIRED.. , 'i
-TECHNICAL STAFF REVIEW T0 BEGIN UPON RECEIPT OFr- i ADDITIONAL SCE&G INFORMATION.
69693 BULLETIN-88-08, " THERMAL STRESSES IN PIPING -
CONNECTED TO REACTOR COOLANT SYSTEMS w
-RESPONSE SUBMITTED 9/29/88. j
-MEETING' HELD 10/6/88.. i
-ADDITIONAL INFORMATION SUBMITTED BY SCE&G 12/19/88.
69782 GENERIC LETTER 88-17, " LOSS OF DECAY HEAT REMOVAL"
-RESPONSE TO EXPEDITIOUS ACTIONS PROVIDED BY SCE&G 1/23/89.
-RESPONSE TO 6 PROGRAM ENHANCEMENTS REQUIRED. 1
-SCE&G TO PROVIDE RESPONSE BY .
69978 BULLETIN 88-04, POTENTIAL SAFETY RELATED PUMP LOSS. -i i'
-WRI? TEN 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 l OF THE LONG TERM RESOLUTION ACTIONS.
-RESPONSE ON EFW PUMPS-PROVIDED 12/20/88.
-RESPONSE REQUIRED ON WHETHER INSTALLED'MINIFLOW CAPACITY IS ADEQUATE FOR SINGLE PUMP OPERATION.
INFORMATION TC 8E PROVIDED FOLLOWING 1990 REFUELING OUTAGE.
- +
f 1
????? BULLETIN 88-03, INADEQUATE LATCH ENGAGEMENT-IN-HFA TYPE LATCHING RELAYS MANUFACTURED BY GE. ,
J
-RESPONSE SENT BY SCE8G 1/13/89
-PM TO WRITE LETTER CLOSING THIS ITEM OUT 2/89.
????? BULLETIN 87-02, SUPPLEMENT 1 " FASTENERS TESTING TO DETERMINE CONFORMANCE APPLICAPLE MATERIAL 3 SPECIFICATIONS" ]
l
-RESPONSE SUBMITTED 7/20/88. 1
????? GENERIC LETTER 88-11. "NRC POSITION ON RADIATION EMBRITTLEMENT OF REACTOR VESSEL MATERIAL AND ITS l IMPACT ON PLANT OPERATIONS. !
-RESPONSE SENT BY SCE&G 1/12/89.
-PM TO CLOSE OUT ITEM IN LETTER 2/89. ._
????? GENERIC LETTER 88-14 " INSTRUMENT AIR SUPPLY SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT" -
-RESPONSE DUE APPROXIMATELY 2/15/E9.
-REQUIRES DESIGN AND OPERATIONS VERIFICATION.
-SCE&G HAS WRITE-UP ON SCHEDULE.
-SCEAG TAXING REPRESENTATIVE SAMPLES AND SEEING HOW THEY AFFECT WORKING SYSTEMS.
????? NRC BULLETIN 88-10. "NON-CONFORMING MOLDED-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.
????? ,
GENERIC LETTER 88-20, " INDIVIDUAL 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.
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 YANTAGE.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.
4 ????? BULLETIN 8.8-09, " THIMBLE TUBE THINNING 1/4/89
.IN WESTINGHOUSE REACTORS".
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' DISTRIBUTION'FOR MEETING
SUMMARY
DATED: ' February .28, 1989 Facility: .V. . C. Sumer:
L. Thygy NRC PDR
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PDII-1 Reading.
E. Adensari lE.' Reeves
. P. Anderson 4 J. Hr.yes
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B;' Grimes (9A2)-
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D.'Verrelli'(Region II)
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