ML20247E702
| ML20247E702 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/21/1989 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8907260265 | |
| Download: ML20247E702 (15) | |
Text
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'i July 21, 1989 1 00cket No. 50-395
*' _ LICENSEE: South Carolina Electric & Gas Company
- FACILITY:-V. C. Summer Nuclear Station, Unit No. 1
SUBJECT:
SUMMARY
OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY . GENERAL j On June 21, 1969,- the NRC staff consisting of representatives of the Office of Nuclear Reactor Regulation (NRR) and Region Il net 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 NRR offices in Rockville, Maryland. A list of those persons 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, This handout is included as Enclosure-2. There was an error in the title of the TAC 71554 listed on Enclosure 1. It should have read "GL 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations." Enclosure 3 is a handout 3rovided by the licensee which listed proposed technical specification c1anges to be submitted and their prioritization of the outstanding TACs. During the meeting there was discussion on the possibility that the next refueling outage may be moved from March 1990 to the Fall of 1990. If this were done, ap)roximately 180 surveillance test procedures would need to be performed before t1e Fall outage in order to be in compliance with the Summer Technical Specifications. It was suggested that the licensee consider contingency plans to work these surveillance into a program to be instituted if the plant should be shutdown between now and March 1, 1990. The next meeting is currently scheduled for August 8,1989, in the Region II offices in Atlanta, Georgia. Original Signed By: John J. Hayes, Jr , Psoject Manager Project Directorate II-1 . Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
DISTRIBUTION: As stated Docket File ' PAnderson FCantrell NRC PDR JHayes PHopkins cc w/ enclosures: Local PDR OGC RPrevatte See next page PD21 R/F EJordan(MNBB3302) ACRS(10) EAdensam BGrimes (9A2) RBorchardt [SUMMERMTG
SUMMARY
) 8907260265 890721 PDR ADOCK 05000395 OIr P PDC ig 21:DRPR : : : : : : .0FC : p Zl:f.RPR:D-4 NAME : @ di :E ensam : : : : : DATE :7//)//89 :7///89 : : : : :
0FFICIAL REC JRD COPY
t i-;* u .L .. .. .. l' t + ' Mr. D. S. Bradham ~ L
.Soutfr Carolina Electric & Gas Crmpany Virgil C. Summer Nuclear Statien
- p. .,: :
i cc: l u Mr. William A. Williams, Jr. i
' Technical Assistant Nuclear Operations Santee Cooper-P. O. Box 764-(Mail l Code'153) ;
!< Columbia, South Carolina 29218 ' J.'B. Knotts, Jr...Esq. ; Bishop. Cook, Purcell- ; and Reynolds. ~
'1400 L Street, N.W. '
Washington, D. C. 20005-3502
- Resident Inspector /Sumer NPS. _
L c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065. >s Regional Administrator, Region II-U.S. Nuciear Regulatory Commission.
.101 Marietta Street, N.W., Suite 2900
. Atlanta, Georgia 30323 Chairman, Fairfield County Council u P. O. Box 293 I k'innsboro, South Carolina 29180.
Attorney General P. 0.. 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 J
l *
, ENCLOSURE 1 ATTENDANCE June 21, 1989 SCE&G NRC A. Koons, Jr. F. Cantrell N. Williams J. liayes, Jr.
c ENCLOSURE 2 e \ l' STATUS OF NRC TACS FOR THE V. C. SUMMER. PLANT June 21, 1989 49976 ISI PROGRAM (M. HUME)
-N0 SCHEDULE FOR THIS REVIEW. ITEM ANTICIPATED TO BE ON THE LIST OF ACTIONS GREATER THAN TWO YEARS OLD.
51287 SPDS(G. WEST)
-SER ISSUED
-THREE OPEN ITEMS
- 1. TOP LEVEL ICONICS ARE NOT CONTINUOUSLY DISPLAYED.
2.
- a. SYSTEM RESPONSE 10 OPERATOR COMMANDS IS VERY SLOW. l
- b. SYSTEM HAS NOT BEEN ABLE TO MEET ITS UNAVAILABILITY GOAL OF LESS THAN 1 %.
- c. LACK 0F 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 h0N-VALID VALUES OR CONDITIONAL FLAGS EXISTED FOR RHR FLOW RATE, SUBC00 LING MARGIN,(REACTOR SYSTEM VESSEL LEVEL INDICATIONRVLIS), STARTUP HYDR 0 GEN,ANDSAFETYINJECTION(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 l
REVISED REVIEW SCHEDULE.
-LICENSEE PROVIDED A MILESTONE SCHEDULE FOR THE INSTALLATION OF THE SPDS ON 3/6/89.
51506 RV AND SV TESTING (II.D.1) (GARY HAMMER) l
-SCE8G SUBMITTED RESPONSE TO STAFF COMMENTS ON 5/9/88.
t
- n
-ADDITIONAL QUESTIONS SUPPLIED TO SCE8G AS A RESULT OF-THEIR 5/9/88 RESPONSE. y
, -DRAFT OF SCE&G RESPONSES TO NRC QUESTIONS GIVEN TO ! HAMMER ON 7/25/88.
-CONFERENCE CALL HELD ON THE RESPONSES 8/10/88.-
]
-SCE&G TRANSMITTED FOLLOWING INFORMATION IN DRAFT FORM:
(1) DRAWING C-314-601 WENT TO EG8G IDAHO 8/11/88; (2) ACCEPTANCE CRITERIA FOR NORMAL, 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 B 0F SCE&G DRAFT RESPONSES.
-SCE&G PROVIDED RESPONSES TO NRC COMMENTS ON 5/31/89.
'53406 AUTO.SHUNTTRIPTS,;GL83-28 ITEM 4.3(D0NLASHER)
-RAI ISSUED.
-CLARIFICATION
-THAT TS TABLE 4.3-1 FUNCTIONAL UNIT H0. I
" MANUAL REACTOR TRIP" APPLIES TO RT BYPASS LREAKERS AS WELL AS RT BREAKERS..
-TS TABLE 4.3-1 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.
-SHOLLY ISSUED 5/89.
-SE 6/6/89.
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 l -TER ISSUED BY EG&G
-0 PEN ITEMS ARE:
-CONTACT VENDORS OF KEY COMPONENTS SUCH AS AFW PUMPS, ECCS PUMPS SAFETY RELATED BATTERIES, L AND SAFETY RELATED VALVES TO FACILITATE THE L
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.
-GENERIC LETTER TO BE ISSUED LATE SUMMER.
-GENERIC LETTER WILL PROVIDE GUIDANCE ON VENDOR
INTERFACE, LICENSEE WILL BE REQUESTED TO CONFIRM BY. LETTER THAN THEY MEET GL, AND NRC MAY INSPECT LICENSEE'S PROGRAM. 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.
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.
-CLOSED OUT WITH SE ISSUED 6/12/89.
55344 PROCEDURES GENERATION PACKAGES (SUPPLEMENT 1, NUREG-0737)(GEORGELAPINSKY)
-DRAFT SE ISSUED 6/29/87.
-PROBLEMS IDENTIFIED INCLUDED:
- 1. PLANT SPECIFIC TECHNICAL GUIDELINES.
- 2. WRITERS GUIDE. 1 1
- 3. PROGRAM USED FOR VALIDATION OF E0Ps.
- 4. TRAINING PROGRAM FOR UPGRADED E0Ps. :
-SCE&G WAS TO RESPOND TO THE STAFF COMMENTS WHEN FURTHER STAFF GUIDANCE IS PROVIDED (SEE BELOW).. !
-NRC TO PERFORM INSPECTION OF 16 FACILITIES TO '
DETERMINE IF A DIFFEREUT 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 TO BE ISSUED BY THE TECHNICAL BRANCH
-SE TO BE ISSUED BY THE PM TWO MONTHS AFTER RECEIPT OF SE FROM TECHNICAL BRANCH.
59402 40 YEAR OL LIFE AMENDMENT
-LICENSEE RESPONDED TO RAI 3/30/88.
-PM TO HOLD 11EETING WITH THE LICENSEE 4/18-4/21 TO DISCUSS THE ADDITIONAL INFORMATION REQUIRED TO EVALUATE THE AMENDMENT REQUEST.
E
p r
-LETTER SENT TO LICENSEE REQUESTING ADDITIONAL INFORMATION 4/20/89..
-LICENSEE COMMITTED TO PROVIDING RESPONSE BY 6/19/89 IN 5/31/89
< LETTER.
-LICENSEE RESPONSE TRANSMITTED 6/15/89.
59451 DIESEL GENERATORS TS (J. LAZEVNICK)
-REQUEST FOR ADDITIONAL.INFORMATION SUBMITTED T0.
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 8Y SPLITTING INTO 2 SEPARATE SURVEILLANCE REQUIREMENTS.
-RE-SH0LLIED 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.
f' -CONFERENCE CALL HELD 12/88. SCE&G TO PROVIDE A REVISED RESPONSE TO DELETE THE WORDS "0R VERIFICATION" FROM TS 4.8.1.1.1-4.8.1.1.3.
-REVISED TS SENT 4/S/89.
-REQUEST RESH0LLIED 4/89.
-AMENDMENT ISSUED 5/30/89.
62803 CONTAINMENT STRUCTURAL'INTEGRITt (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.
-SCE&G SUBMITTAL OF 9/29/88 ADDRESSED PREVIOUS CONCERNS..
-SE RECEIVED FROM TECHNICAL BRANCH 12/19/89.
-SE ISSUED 4/28/89.
64821 RSB 5-1, NATURAL CIRCULATION TEST OF THE REACTOR COOLANT
-REACTOR SYSTEMS BRANCH TO REVIEW THIS ITEM.
-CONFERENCE CALL TO BE HELD WEEK OF 6/19/89.
65060 REMOVAL OF FIRE PROTECTION REQUIREMENTS FROM THE TS GL 86-10
-RE-SH0LLIED 2/24/88.
-ANENDMENT TO HAVE BEEN ISSUED 5/88.
-CONCURRENCE STOPPED DUE TO FORTHCOMING GUIDANCE IN GENERIC LETTER TO BE ISSUED.
r
-GENERIC 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 TO BE ISSUED 6/89.
65778 REMOYAL OF ORGANIZATIONAL CHARTS FROM THE TS
-SCE&G PROVIDED RESPONSE BASED UPON GL 88-06 ,
ON 5/16/88..
-RE-SHOLLIED 8/25/88. i
-SUBMITTAL RECEIVED FROM SCE&G 12/22/88.
-SE TO BE ISSUED 6/89.
67340 ORGANIZATIONAL CHARTS TO REFLECT 1/25/88 REORGANIZATION 1
-SUBMITTAL RECElVED FROM SCE8G 12/22/88.
-SE TO BE ISSUED 6/89.
67812 ISI RELIEF, HYDROSTATIC TESTING OF THE SGB SYSTEM (M. HUME) RELIEF GRANTED 6/ /89. 68046 IST 12/23/87 PROGRAMREVISION(K.DEMPSEY)
-5ER ISSUED 4/19/88
-SOME RELIEFS DENIED, SOME GRANTED l
-LICENSEE MUST ADDRESS APPENDIX C 0F THE TER WHICH COVERS 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 SCE8G 8/31/88.
-ADDITIONAL INFORMATION REQUESTED VIA THE TELEPHONE ON 6/15/89 FOR EG&G TO COMPLETE THE REVIEW.
68610 IMPLEMENTATION OF STATION BLACK 0UT RULE, 10 CFR 50.63, A-22 (A. GILL) l
-RESPONSE TRANSMITTED 4/17/89.
68834 BULLETIN 88-05, NON-CONFORMING MATERIALS SUPPLIED l BY PIPING SUPPLIES, INC. AT FOLSOM, N.J. AND WEST JERSEY j MANUFACTURING CO. AT WILLIAMSTOWN, N. J., B-104.
L: ) t
- -];
p.
'^
-RESPONSE SUBMITTED 9/13/88.
-WRITTEN RESPONSE DUE 60 DAYS AFTER COMPLETION OF ALL SCHEDULED ACTIONS. i
-INSPECTION CONDUCTED BY SCE&G 10/08. ,
L -LICENSEE SENT LETTER ON RESULTS OF INSPECTION OF l N0ZZLE PLATES ON 3/6/89. l 69066 STEAM GENERATOR, L* (H. CONRAD)
-ENVIRONMENTAL ASSESSMENT PUBLISHED IN THE FEDERAL REGISTER 10/88.
-CONFERENCE CALL HELD 10/2S/88.
-PRELIMINARY REVIEW INDICATES THAT ADDITIONAL INFORMATION IS REQUIRED.
-TECHNICAL STAFF REVIEW TO BEGIN UPON RECEIPT OF ADDITIONAL SCE&G INFORMATION.
-ADDITIONAL INFORMATION TRANSMITTED 6/13/89.
69693 BULLETIN 88-08, " THERMAL STRESSES iN PIPING CONNECTED TO REACTOR COOLANT SYSTEv.S
-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 7/89.
H 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 PROVIDED BY LICENSEE 2/2/89.
-NRC COMMENTS ON EXPEDITIOUS ACTIONS TO BE SENT TO LICENSEE 7/89.
69978 BULLETIN 88-04, POTENTIAL SAFETY RELATED PUMP LOSS.
-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 PROVIDED 12/20/88.
-RESPONSE REQUIRED ON WHETHER INSTALLED MINIFLOW CAPACITY IS ADEQUATE FOR SINGLE PUMP OPERATION.
INFORMATION TO BE PROVIDED FOLLOWING 1990 REFUELING OUTAGE.
,, m - . . _ . - .- _._ -_--_ _ _ n pf ' .,, e 71360. NRC BULLETIN 88-10,.."NON-CONFORMING MOLDED-CASED LCIRCUIT BREAKERS".
' -LETTER SENT TO SCE&G REQUESTING <THAT INFORMATION
-BE PROVIDED AS'IT BECOMES AVAILABLE.
-RESPONSE TRANSMITTED 3/31/89.
171725 GENERIC LETTER'88-14, " INSTRUMENT AIR SUPPLY' SYSTEM
~ PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT"
-RESPONSE SENT 2/2/89.
-AFFECTED VALVES AND COMPONENTS TO BE ADDED'TO THE PREVENTATIVE MAINTENANCE PROGRAM BY 4/26/89.
-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).- y
-LETTER SENT.TO LICENSEE ON 3/31/89 REQUESTING THAT 1
.THE LICENSEE INFORM THE NRC WHEN ALL REQUIREMENTS ARE IMPLEMENTED.
72171- NRC BULLETIN 88-11,
- PRESSURIZER SURGE LINE THERMAL STRATIFICATION"
-LICENSEE KESPONDED 3/1/89.
-SUBMITTED RESPONSE TO 1.A 0F BULLETIN.
-LICENSEE INTENDS TO WORK WITHIN WOG.
-ALTERNATE SCHEDULE PROPOSED FOR 1.B 0F BULLETIN.
-LETTER SENT 6/12/89 DETAILING AGREEMENT BETWEEN NRC AND THE :
WESTINGHOUSE OWNERS GROUP. LICENSEES ARE TO SUBMIT THEIR RESPONSE ! TO ITEM l'.b 0F THE BULLETIN WITHIN 1 YEAR AS ORIGINALLY REQUIRED. -{ 72727 AMENDMENTONDCSOURCES(TS3/4.8.2) i
-APPLICATION SENT 8/24/88. i
-SHOLLY ISSUED 5/3/89. l
-AMENDMENT TO BE ISSUED 7/89. i 72893 FEEDWATERISOLATIONVALVES(TS3.7.1.6)
-REQUEST SUBMITTED 4/5/89. .
-SHOLLIED 5/3/89.
-AMENDMENT T0 BE ISSUED 7/89.
73209 FAILURE OF WESTINGHOUSE STEAM GENERATOR TUBE MECHANICAL PLUGS (BULLETIN 89-01)- I
---a.n_--._ _-__.a,_-__--- - - - -:-.a -._
g... 7 V^ . 4,
-RESPONSE TO ACTION'1 ON THE HEATS OF PLUGS IN'THE SG DUE 6/15/89.
-RESPONSE TO ACTIONS 2-4 DUE AT THE NEXT REFUELING OUTAGE.
h- ! 73300 SERVICE WATER SYSTEM BIOCIDE T:1EATMENT L -REQUEST FOR APPROVAL SUBMITTED 5/19/89. 73301' TS 4.0.3 AND 4.0.4 AMENDMENT..
-REQUEST SUBMITTED 5/22/89.
p -SHnt, LIED 6/89. l
????? BULLETIH 87-02, SUPPLEMENT 1, " FASTENERS TESTING TO DETERMINE CONFORIMNCE APPLICABLE MATERIAL SPECIFICATIONS"
-RESPONSE SUBMITTED 7/20/88.
????? GENERIC LETTER 88-20, " INDIVIDUAL PLANT EXAMINATION FOR SEVERE ACCIDENT VULNERABILITY".
i
????? GENERIC LETTER 89-08, " EROSION / CORROSION INDUCED PIPE WALL THINNING
-REPLY REQUIRED BY 7/2/89 AS TO WHETHER A LONG TERM f40NITORING PROGRAM HAS BEEN IMPLEMENTED EQUIVALENT TO THE hufMRC. IF NOT, THEN SHEDULE FOR IMPLEMENTATION.
TACS CLOSED
-TAC NO. DESCRIPTION OF THE TAC DATE CLOSED 56935 RCP TRIP CRITERIA, GL 83-100 03/15/89 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 68045 SINGLE CELL CHARGING OF SAFETY RELATED 04/03/89 BATTERIES. 68274 SG TUBE SLEEV1HG. 11/10/88 68644 ANTAGE 5 FUEL, REMAINING TS SECTIONS. 10/28/88 l
I 68956 BORIC ACID CORROSION OF C-STEEL 10/06/88 COMPONENTS IN PWR PLANTS GL 88-05. I 71554 NRC BULLETIN 88-10, "NON-CONFORMING 02/07/89 MOLDED-CASE CIRCUlT BREAKERS". 72685 BULLETIN 88-09, " THIMBLE TUBE THINNING 01/04/89 IN WESTINGHOUSE REACTORS".
????? BULLETIN 88-03, INADEQUATE LATCH 02/06/89 ENGAGEMENT IN HFA TYPE L/ ITCHING RELAYS MANUFACTURED BY GE.
_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _._m_._.._.._
i- 1 Lj . ENCLOSURE 3
]
n,3 ' Technical Specification Chanaes to be Submitted s :
# F*. Renewal i ' Steam Generator Sleeving Amendment
# RTD Bypass Elimination
# RHR Suction Interlocks
#- Condensate Storage Tank Low Level Setpoint for Auto EFWS Suction Swap to Service Water Diesel Generator Fuel Oil Volume Change Diesel Generator Fuel Oil Analysis Change ESF Surveillance Relaxstion -. Westinghouse Owners Groups
# Control Rod Repositioning Containment Negative Pressure Post Accident Monitoring Table Main Steam Isolation Valves i Refuel V Items
.i
p-J y . y .:
.a w PRIORITY TAC NO. ITEM l 1 59402 40 Year OL Life Amendment 2 69066 Steam Generator, L*
, , 3- 65060 Removal of Fire Protection Requirement 4 65778 Removal of Organization Charts 5 67340- Reorganization 6 1 73300 Service Water System 3iocide Treatment 7 72893 Feedwater Isolation Valves 8' 72727- Amendment on DC Sources 9 67812 ISI Relief, Hydro Test of' Steam Generator BD~ System-10 73301 .TS 4.0.3 and 4.0.4 Amendment 11 68046 IST Program 12 69782 GL'88-17. " Loss of Decay Heat Removal" 13 68610 Blackout Rule 14 55344- Procedures Generation Package 15 51606 RV and SV Testing 16 68834 IEB 88-05, " Nonconforming Materials..." 17- 71725 GL 88-14. " Instrument Air Supply System..." 18 53942 Preventive Maintenance Program for Reactor Trip Breakers 19 69978 IEB 88-04, " Potential. Safety Related Pump Loss" 20 71360- IEB 88-10. " Nonconforming Molded-Case Circuit Breakers" 21 72171 IEB 88-11. " Pressurizer Surge Line Thermal Stratification" 22 49976 ISI Programs 23 51287- SPDS 24 64821 RSBS-1 Natural Circulation Test 25 53720 Item 2.2 of GL 83-28, " Equipment Classification
& Vendor Interface"
7,_ s, I' DISTRIBUTION FOR MEETING
SUMMARY
DATED: July 21,1989
. Facility: V. C. Sunner*
Docketdile. NRC & Local PDRs-J. Sniezek,= 12/G/18-
'PD11-1 Reading E. Adensam J. Hayes'
'P.-Anderson OGC E. Jordan, MNBB-3302 NRC Participants ACRS'(10)
R. Borchardt, 17/G/21
- Copies sent to persons on' f acility service list DPo' I i
-l 1
_ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}