ML20011E375
| ML20011E375 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/02/1990 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9002130306 | |
| Download: ML20011E375 (15) | |
Text
_
1 February 2, 1990 Docket No. 50-395 LICENSEE: South Carolina Electric & Gas Company FACILITY: V. C. Summer Nulcear Station, Unit No.1
SUBJECT:
SulHARY OF JANUARY 31, 1990 MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL On January 31, 1990, a representative of the Office of Nuclear Reactor Regulation (NRR) net with a representative of the South Carolina Electric
& Gas Company (SCE&G) to discuss the status of the licensing issues for i
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 1
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.
Discussions were also held on the amendment submittals involving the March 1990 refueling outage.
The next meeting is currently scheduled for March 1990, either in Region II of fices in Atlanta, Georgia or at the V.C. Summer Station.
Original Signed By:
L John J. Hayes, Project Manager L
Project Directorate 11-1 l ~
Division of Reactor Projects -1/11
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Office of Nuclear Reactor Regulation l
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Enclosures:
L As stated
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1 DISTRIBUTION L
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SUMMER
SUMMARY
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y February 2,1990 Docket No.
50-395 LICENSEE: South Carolina Electric & Gas Company L
FACILITY: V. C. Sumner Nulcear Station, Unit No. I j
SUBJECT:
SUMMARY
OF JANUARY 31, 1990 MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY i
GENERAL On January 31, 1990, a representative of the Office cf Nuclear Reactor Regulation (NRR) met with a representative of the South Carolina Electric I
& Gas Cotopany (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 actior.s. This handout is included as.
Discussions were also held on the econdment submittals involving the March 1990 refueling outage.
The next u*eting is currently scheduled for March 1990, either in Region II offices in Atlanta, Georgia or at the V.C. Summer Station.
P
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L' John J. Ha es, Pro ct Manager
.Project Directorate 11-1 Division of Reactor Projects -I/II Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enc 1s:
See next page I
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C. Haughney 11-E-22 OGC 15-B-18 E. Jordan NNBD-3302 ACRS (10)'
P-315 GPA/PA 17-F-2 V. Wilson 12-H-5 L. Thomas 12-E-4 B. Borchardt 17-D-19
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South Carolina Electric & Gas Company Virgil C. Sumer Nuclear. Station i
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Executive Vice President
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P. O. Box 398) l Honcks Corner, South Carolina 29461-0398
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J. B. Knotts, Jr...Esq.
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1400 L Street. N.W.
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Resident-Inspector / Summer NPS c/o U.S. Nuclear Regulatory Counission Route 1, Box 64 Jenkinsv111e, South Carolina 29065 Fagional Administrator, Region II U.S. heclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairun, Fairfield County Council P. O. Dox 293.
Winnsboro, South Carolina 29180 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2000 Bull Street
. Columbia, South. Carolina 29201 South Carolina Electric & Gas Company v
Mr. - A. - R. Koon, Jr., Manager Nuclear Licensing Virgil C. Sumer Nuclear Station P.--0. Box 88-Jenkinsville, South Carolina 29065 i
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STATUS OF NRC TACS FOR ThE V. C. SUMMER PLANT Janua ry 31, 1990 v
49976 ISI PROGRAM (M. HUME)
-ITLM NOW GIVEN LOW PRIORITY.
51606 RV AND SV TESTING (ll.D.1) (GARY HAMMER X-10319) 1'
-SCE&G SUBMITTED RESP 016E TO STAFF C0leENTS ON 5/9/68.
-ADDITIONAL QUESTIONS SUPPLIED TO SCE&G AS A RESULT 0F THEIR 5/9/88 RESPONSE.
-CRAFT OF SCE8G RESPONSES TO NRC QUESTIONS GIVEN TO HAMMER ON 7/25/88.
-CONFERENCE CALL HELD ON THE RESPONSES 8/10/88.
-SCE&G TRANSMITTED FOLLOWI!4G INFORMATION IN DRAFT FORM:
(1) DRAWING C-314-601 WENT TO EG&G, IDAHO 8/11/88; (2) ACCEPTANCE CRITERI A FOR NORMAL, EMERGENCY, AND UPSET CONDIT1016 ON 9/21/08 TO G. HAMMER; (3) EXPLAtATION OF DISCREPANCIES DETWEEN RESPONSES TO QUESTIONS 6 AND 9 AND FSAR TABLE 5.2.3 CN 9/21/88 TO G.
i HAMMER.
-NRC PROVIDED COMMENTS ON PESPONSE TO ITEM B 0F SCE&G DRAFT RESP 0f.SES.
-SCE8G PROVIDED RESPONSES TO NRC C0llMENTS ON 5/31/89.
-5E ISSUED 1/19/90.
53720 ITEM 2.2 0F GL 83-28. EQUIP. CLASSIFICATION AND VENDOR INTERFACE FOR SAFETY RELATED COMPONENTS (SCOTT NEWBERRY X-20787)
-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 PUWS SArETY RELATED DATTERIES, AND SAFETY RELATED YALVES TO FACILITATE THE EXCHANGE OF CURRENT TECHNICAL INFORMATION.
AN INFORMAL INTERT/sCE AGREEMENT SHOULD BE ESTABLISHED.
-FOR DGs AND SAFETY RELATED SWITCHGEAR VENDORS A FORMAL INTERFACE SIMILAR TO THAT W11H THE NSSS SHOULD BE ESTABLISHED.
-GENERIC LETTER TO BE ISSUED.
-GENERIC LETTER WILL PROVIDE GUIDANCE ON VENDOR INTERFACE, LICENSEE WILL BE REQUESTED TO CONFlf.M CY LETTER THAN THEY MEET GL, AND NRC MAY INSPECT
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LICENSEE'S PROGRAM.
l 53942 ITEMS 4.2.3 & 4.2.4 0F GL 83 28, PREVENTIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS) L TESTING & REPLACEMENT (C. H0RRIS X-23284
-BULLETIN 15 BEING PREPARED TO SEND TO CRGR.
55344 PROCEDURES GENERATION DACKAGES (SUPPLEMENT 1, NUREG- 0737) (GREG GALLETTI X. 21128)
-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. TRAIN!NG PROGF;AM FOR UPGRADED E0Ps.
-SCE&G WAS TO RESP 0hD TO THE STAFF COMMENTS WHEN FURTHER STAFF GUIDAhCE IS PROVIDED (SEE BELOW)..
-NDREG TO BE ISSULD 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 COWENTS OR MAINTAIN A COPY OF THE JUSTIFICATION AS TO WlY THE C0ftENTS WERE NOT INCORPORATED.
-SUMER SE TO BE ISSUED BY THE TECHNICAL BRANCH.
59402 40 YEAR OL LIFE AMENDHENT
-LICENSEE RESPONDED TO RAI 3/30/88.
-PM HELD MEETING WITH THE LICENSEE THE WEEK 0F 4/18-4/21 TO DISCUSS THE ADDITIONAL INFORMATION REQUIRE 0 TO EVALUATE THE AMENDMENT RE0 VEST.
-LETTER SENT TO LICENSEE REQUESTING ADDITIONAL INFORMATION 4/20/89.
-LICENSEE COMMITTED TC PROVIDING RESPONSE BY 6/19/89 IN 5/31/89 LETTER.
-LICENSEE RESPONSE TRANSMITTED 6/15/89.
-REQUEST FOR ADDITIONAL lhFORMATION TRANSMITTED 8/16/89.
-LICENSEE TRANSMITTED A RESPONSE ON 9/1/89.
-AMEhDMENT ISSUED 1/3/90.
64821 RSB 5-1, NATURAL CIRCULATION TEST OF THE REACTOR COOLANT
-REACTOR SYSTEMS BRAhCH TO REVIEW THIS ITEM.
-CONFERENCE CALLS HELD 6/21/89, 7/19/89 AND 8/29/89.
-SCHEDULE FOR SU5MITTAL BY LICENSEE IS 12/89.
-SUBMITTAL MADE 1/25/90.
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68046 IST 12/23/87 PROGRAM REVISION (K. DElf SEY X-20918)
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-SER ISSUED 4/19/88
-SOME RELIEFS DENIED, SOME GRANTED
-LICENSEE MUST ADDRESS APPENDIX C 0F THE TER WICH COVERS OMISSIONS AND INCONSISTENCIES IN THE PROCRAM.
-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.
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-ALDITIONAL INFORi% TION REQUESTED VIA THE TELEPH0hE ON 6/15/89 FOR EGtG TO COMPLETE THE REVIEW.
-PROCEDURE GTP 302 TRANSMITTED BY LICENSEE 7/19/69, i
68610 IMPLEMENTATION OF STATION BLACK 0UT RULE,10 CFR 50.63, A-22 (A. GILL) l
-RESP 0 HSE TRANSMITTED 4/17/89.
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-REVISED RESPONSE TRANSMITTED BY SCE&G 10/2/89 68034 BULLETIN 88-05, NON-CONFORMING MATERI ALS SUPPLIED BY PIPING SUPPLIES, INC. AT FOLSOM, N.J. AND WEST JERSEY MANUFACTURING CO. AT WILLI At$10WN, N. J., B-104.
-RESPONSE SUBMITTED 9/13/88.
-WRITTEN RESPONSE DUE 60 DAYS AFTER COMPLETION OF ALL SCHEDULED ACTIONS.
-INSPECTION CONELCTED BY SCE&G 10/88.
-LICENSEE SENT LETTER ON RESULTS OF INSPECTION OF 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 INDICATES THAT ADDITIONAL INFORMATION IS REQUIRED.
-TECHNICAL STAFF REVIEW TO EEGIN UPON RECEIPT OF ADDITIONAL SCE&G INFORMATION.
-AODITIONAL-INFORMATION TRANSMITTED 6/13/89.
-MEETING HELD 10/5/89 WHERE IT WAS DETERMINED THAT ADDITIONAL l-INFORMATION IS REQUIRED TO DEMONSTRATE THE ADEQUACY OF THE USE OF i
EDDY CURRENT TESTING TO DETERMINE SG TUBE CRACK SIZE AND ORIENTATION.
-AWAITING INFORMATION.
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-LETTER TRANSMITTED 1/12/90 INDICATED THAT ADDITIONAL INFORMATION I
WILL BE SUBMITTED 8/90.
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69693 BULLETIN 88-08, " THERMAL STRESSES IN PIPING CONNECTED TO PEACTOR COOLANT SYSTEPS
-RESPONSE SUBMITTED 9/29/88.
-MEETING HELD 10/6/88.
1
- ACDITIObAL INFORMATION SUBMITTED BY SCE&G l
12/19/88.
-DIFFERENTIAL TEMPERATURE DATA SUBMITTED ON 3/23/89.
69782 GENERIC LETTER 88-17, " LOSS OF DECAY HEAT REMOVAL"
-RESPONSE TO EXPEDITIOUS ACTIONS PROVIDED BY SCE8G 1/23/89.
-RESPONSE TO 6 PROGRAM ENHAhCEHENTS PROVIDED BY LICENSEE 2/2/89.
-NRC COMMENTS ON EXPEDITIOUS ACTIONS SENT TO LICENSEE 6/26/89.
69978 CULLETIN 86-04, POTENTI AL SAFETY PELATED PUMP LOSS.
-KRITTEN kESPONSE DATED 7/8/88.
-RESPONSE ON EFW PUMPS PROVIDED 12 /2 0/88.
-RESPONSE REQUIRED ON WHETHER INSTALLED MINIFLOW CAPACITY IS ADEQUATE FOR SINGLE PUMP OPERATION.
INFORMATION TO BE PROVIDED FOLLOWING 1990 REFUELING OllT/GE.
71360 NRC BULLETIN 88-10. "NON-CONFORMING MOLDED-CASED CIRCUIT BREAKERS".
-LETTER SEhT TO SCE&G REQUESTING THAT INFORMATION BE PROVIDED AS IT BECOMES AVAILABLE.
-RESPONSE TRANSMITTED 3/31/89.
i
-SUPPLEMENT 10F THE BULLETIN ISSUED 8/3/89.
-BY APPR0XIHATELY 11/10/89 LICENSEE MUST VERIFY PREVIOUS RESPONSE TO THE BULLETIN IN RESPONSE TO SUPPLEMENT 1.
71725 GENERIC LETTER 88-14
" INSTRUMENT AIR SUPPLY SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT"
-RESPONSE SENT 2/2/89.
1.
AFFECTED VALVES AND COMFtNENTS TO BE ADDED TO THE PREVENTATIVE MAINTENANCE PROGRAM 8Y 4/28/89.
2.
PERIODIC DE} POINT MONITORING AND SYSTEM BLOWDOWN AT SELECTED LOCATIONS INITI ATED BY 8/1/89.
3.
FULL IPPLEMENTATION OF A QUALITY RELATED PROGRAM FOR DI APHRAGMS BY THE FIFTH REFUELING OUTAGE (4/90).
-LETTER SENT TO LICENSEE ON 3/31/89 REQUESTING THAT THE LICENSEE lhFORM THE hRC WHEN ALL REQUIREMENTS ARE IMPLEMENTED.
f 72171 NRC BULLETIN 88-11, " PRESSURIZER SURGE LINE THERMAL STRATIFICATION" i
-LICENSEE RESPONCED 3/1/89.
-SUBHITTED 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 CROUP. LICENSEES ARE TO SUBMIT THEIR RESPONSE TO ITEM 1.b 0F THE BULLETIN WITHIN 1 YEAR AS ORIGINALLY REQUIRED.
-RESPONSE TRANSMITTED TO ITEM 1.b 0F THE GL OH 1/3/90.
72893 FEEDWATER ISOLATION VALVES (TS 3.7.1.6)
-REQUEST SUBMITTED 4/S/89.
-SHOLLIED S/3/89.
73300 SERVICE WATER SYSTEM BIOCIDE TREATMENT
-REQUEST FOR APPROVAL SUBMITTED 5/19/89.
-CONFERENCE CALL 9/18/89 REQUESTED BETZ SUBMITTAL TO EPA FOR REGISTRATION OF THE BIOCIVE AND THE EPA RESPONSE BACK TO THAT REQUEST.
-COPY OF STATE APPROVAL RECEIVED 11/14/89.
73713 GENERIC LETTER 89-06, " TASK ACTI0h PLAN ITEM I.D.2 - SPDS".
-RESPONSE TRANSHITTED 7/7/89.
-LICENSEE TO TRANSMIT DESCRIPTION OF REVISED PROGRAM FOR OPERATION FOLLOWING MARCH 1990 REFUELING OUTAGE.
74068 GEliERIC LETTER 89-13, " SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMENT".
-RESPONSE DUE BY 2/1/90 IfiDICATING THAT STEPS 1-S OF THE GL HAVE BEEN IMPLEMENTED.
74318 BULLETIN 89-02, " STRESS CORROSION CRACKING OF HIGH HARDNESS TYPE 410 STAINLESS STEEL INTERNAL PRELOADED BOLTING IN ANCHOR DARLING MODEL 350 W SWING CHECK VALVES OR VALVES OF SIMILAR DESIGN".
-INSPECTION OF CHECK VALVES DUE AT THE NEXT OUTAGE OF DURATION GREATER THAN 4 WEEKS.
-RESULTS OF INSPECTION DUE WITHIN 60 DAYS OF THE COMPLETION OF THE INSPECTION.
-CLOSED OUT 10/27/89
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74475 GENERIC LETTER 88-20, " INDIVIDUAL PLANT EXAMINATION FOR SEVERE ACCIDENT VULNERABILITY".
-RESPONSE DUE DUE 60 DAYS FROM FEDERAL REGISTER NOTICE ON AVAILABILITY OF NUREG-1335.
-RESPONSE TRANSMITTED 10/31/89.
-LETTER SDiT TO LICENSEE 1/12/90 STATING THAT LICENSEE SHOULD CONSIDER MORE THAN 5 CONTAINMENT EVENT TREE MODES.
74538 GENERIC LETTER 89-21, " REQUEST FOR INFORMATION CONCERNIlG STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUES (USI) REQUIREMENTS"
-MRC DATA PROVIDED TO SCE&G ON 11/17/89 AT THE SITE.
I
-SCE&G TRANSMITTED RESPONSE TO GL ON 11/22/89.
74550 RELIEF REQUEST CN MAIN STEAM DRAIN VALVES, ASME SECTION XI.
-RELIEF ISSUED 12/1A/89.
74564 BULLETIN 89-03 " POTENTIAL LOSS OF REQUIRED SHUTDOWN MARGIN DURING REFUELING OPERATIONS" (D. LABARGE X-21421) 1
-WITHIN 60 DAYS OF THE RECEIPT OF THE BULLETIN (APPROXIMATELY
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1/21/90) NOTIFY THE NRC THAT THE FOLLOW!hG ACTIONS HAVE OR WILL BE TAKEN:
1.
INTERMEDIATE FUEL ASSEMBLY CONFIGURATIONS HAVE BEEN IDENTIFIED Afo EVALUATED TO ASSURE A BORON CONCENTRATION TO ASSURE A 111NIMUM SHUTDOWN MARGIN OF 5%.
2.
ASSURE THAT FUEL LOADING PROCEDURES ONLY ALLOW INTERMEDIATE FUEL ASSEMBLY CONFIGLEATIONS WHICH DO NOT VIOLATE ALLOWABLE SHUTDOWN MARGIN AND THAT THESE PROCEDURES ARE STRICTLY ACHERED TO.
3.
ASSURE THAT STAFF RESP 0llSIBLE FOR REFUELING OPERATIONS ARE TRAINED IN PROCEDURES NOTED IN ITEM 2 ABOVE.
-CLOSED OUT 1/21/90.
L 74577 F* EXTENSION (H. CONRAD X-20929)
-SHOLLIED 10/18/89.
-ADDITIONAL DATA TRANSMITTED 10/27/89.
-CONFERENCE CALL HELD 12/18/89.
-LICENSEE PROVIDED ACDITIONAL INFORMATION 1/5/90.
74578 LOSS OF OFFSITE POWER EVENT 7/11/89
-REQUEST FOR ADDITIONAL INFORMATION REQUESTED 9/6/89.
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j 74475 GENERIC LETTER 88-20. " INDIVIDUAL PLANT EXAMINATION FOR SEVEkE ACCIDENT YULNERABILITY".
-RESPONSE DUE DUE 60 DAYS FROM FEDERAL REGISTER NOTICE ON AVAILABILITY OF NUREG-1335.
-RESPONSE TRANSMITTED 10/31/89.
-LETTER SENT TO LICEhSEE 1/12/90 STATING THAT LICENSEE SHOULD CONSIDER MORE THAN 5 CONTAlf; MENT EVENT TREE MODES.
74538 GENERIC LITTER 89-21. " REQUEST FOR INFORMATION CONCERN!!G STATUS Of i
IMPLEMENTATION OF UNRESOLVED SAFETY ISSUES (USI) REQUIREMENTS"
-NRC DATA PROVIDED TO SCE8G ON 11/17/89 AT THE SITE.
-SCE&G TRAhSMITTED RESPONSE TO GL CN 11/22/E9.
74559 RELIEF REQUEST ON MAIN STEAM DRAIN VALVES, ASME SECTION XI.
-RELIEF ISSUED 12/14/89.
74564 BULLETIN 89-03, " POTENTIAL LOSS OF REQUIRED SHUTDOWN MARGIN DURING REFUELING OPERATIONS" (D. LABARGE X-21421)
-WITHIN 60 DAYS OF THE RECEIPT OF THE BULLETIN ( APPROXIMATELY 1/21/90) NOTIFY THE NRC THAT THE FOLLOWING ACTIONS HAVE OR WILL BE TAKEN:
1.
INTERMEDIATE FUEL ASSEMBLY CONFIGURATIONS HAVE BEEN IDENTIFIED AtiD EVALUATED TO ASSURE A BORON CONCEhTRATION TO ASSURE A HINIMUM SHUTDOWN MARGIN OF 5%.
2.
ASSURE THAT FUEL LOADING PROCEDURES ONLY ALLOW IllTERMEDI ATE FUEL ASSEMBLY CONFIGURATIONS WHICH DO NOT VIOLATE ALLOWABLE SHUTDOWi MARGIN AND THAT THESE PROCEDURES ARE STRICTLY ADHERED TO.
3.
ASSURE THAT STAFF RESP 0HSIBLE FOR REFUELING OPERATIONS ARE J
TRAINED IN PROCEDURES t0TED IN ITEM 2 AB0VE,
-CLOSED OUT 1/21/90.
74577 F* EXTENSION (H. CONRAD X-20929)
-SHOL LIED 10/18/89.
-ADDITIONAL DATA TRANSMITTED 10/27/89.
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-CONFERENCE CALL HELD 12/18/89.
-LICENSEE PROVIDED ADDITIONAL INFORMATION 1/5/90.
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74578 LOSS OF 0FFSITE POWER EVENT 7/11/89
-REQUEST FOR ADDITIONAL INFORMATION REQUESTED 9/6/89,
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-ADDITIONAL INFORMATION TRANSMITTED BY SCE&G 11/9/89.
-CONFERENCE CALL HELD 1/3/90.
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-ADDITIONAL INFORMA110N 1RANSMITTED 1/19/90.
74735 GENERIC LETTER 69-07, " POWER REACTOR SAFEGUARDS CONTINGENCY PLANNING ic FOR SURFACE VEHICLE BOMBS".
-SUPPLEMENT 1 ISSUED 8/21/89.
-RESPONSE TO GL TRANSMITTED 10/30/89.
-CLOSED OUT 1/ci/90.
-74821 RENUMBERING OF 3/4.7.11
-REVISED SUBMITTAL 12/11/89.
-SHOLLIED 1/10/90.
74822 TS 3.7.1.5 MSIV MODES 2/3 74823 TS SR 4.8.1.1.2.0 DG FUEL OIL SAMPLING, ANALYSIS, ETC.
I
-REVISED SUBNITTAL REQUIRED.
-SHOLLIED 1/10/90.
74824 TS 3/4.5.2 REMOVAL OF RHR SYSTEM AUTOCLOSURE INTERLOCK (ACI),
-SHOLLIED 10/18/69.
-CONFERENCE CALL HELD 11/21/89.
-SCE&G TO PROVIDE CLARIFYING INFORMATION FIRST WEEK OF DECEMBER.
-REVISED SUBMITTAL 12/11/89.
74825 TS 3.8.1 & 3.8.2 DG FUEL OIL STORAGE YOLUME
-REVISED SUBMITTAL 12/11/89.
-SHOLLIED 1/10/90.
74826 TS TABLES 2.2-1 & 3.3-4, REPLACEMENT OF RTDs FOR RTD BYPASS MANIFOLD
-SH0LLIED 10/18/89.
-REQUEST FOR ADDITIONAL INFORMATION TRANSMITTED 12/7/89.
-REVISED SUBMITTAL 12/11/69.
-LICENSEE PROVIDED ADDITIONAL DATA ON 1/2/90 IN RESPONSE 12/7/89 RAl.
74839 TS 4.4.5.4 SG TUBE SLEEVES, B&W (H. CONRAD X-20929)
-REVISED SUBMITTAL 12/11/89.
-SHOLLIED 1/10/90.
- ADDITIONAL INFORMATION TRANSMITTED BY LICENSEE ON /16/90.
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75004 GENERIC LETTER 89-19 " SAFETY IMPLICATIONS OF CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS" (K. JABBOUR X-21496)
-LICENSEE TO PROVIDE BY 3/20/90 SCHEDULE FOR IMPLEMENTING RECOMMENDATIONS IN ENCLOSURE 2.
-COMMITMENTS MADE SHOULD BE IMPLEMENTED PRIOR TO STARTUP AFTER TFE FIRST REFUELING OUTAGE BEGINNING 9 MONTHS AFTER THE RECEIPT OF THE GL. (9/91 FOR SUMMER) 75049-TS ON DELETION OF CYCLE SPECIFIC PARAMETERS
-SHOLLIED 10/18/89.
-C0hFERENCE CALL HELD 10/11/69.
-REVISED SUBMITTAL TRANSMITTED BY SCE&G 10/19/89.
-REVISED SUBMIT 1AL 12/11/89.
75061 REQUALIFICATION SCHEDULE
-RESPONSE PROVIDED 8/18/89 TO GL 89-12. "0PERATOR LICENSING EXAMINATIONS WHICH REQUESTED AN EXTEhSION TO THE ANNUAL TRAINING CYCLE.
-LETTER TRAhSMITTED TO SCE&G 10/26/89 INQUIRING AS TO WHETHER AN EXEMPTION WAS REQUESTED AND/0R A CHANCE IN PROGRAM CYCLE.
-LICENSEE'S 11/9/89 RESPONSE REQUESTED AN EXEMPTION FOR THE ANNUAL REQUALIFICATION EXAM AND THE 24 MONTH REQUALIFICATION CYCLE.
75359 TS 3/4.3.3.6 TABLES 3.3-10 AND 4.3.7, RB/RHR SUMP LEVEL
-SH0LLIED 1/10/90.
75360 TS 4.7.15, MSIV STROKE TIME TEST
-SHOLLIED 1/10/90.
75361 TS 4.0.2, 3,25 SURVEILLANCE TIME LIMIT
-SHOLLIED 12/27/89.
75723 GENERIC LETTER 89-10, " SAFETY RELATED HOV TESTING AND SURVEILLANCE"
-RESPONSE SENT 12/22/89.
-CLOSE0VT 7/94
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BULLETIN 87-02, SUPPLEMENT 1, " FASTENERS TESTING TO DETERMINE-CONFORHANCE APPLICABLE >%TERIAL SPECIFICATIONS"
-RESPONSE SUBMITTED 7/20/88.
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AMENDMENT ON INCthERATION OF CONTAMINATED OIL i
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-APPLICATION MADE 1/4/90.
TACS CLOSED l
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DESCRIPTION Of THE TAC DATE CLOSED 74318 BULLETIN 89-02, " STRESS CORROSION 10/27/89 CRACKING OF ll!GH HARDNESS TYPE 410 STAINLESS STEEL INTERNAL PRELMDED BOLTING IN ANCHOR DARLING MODEL 350 i
W SWING CitECK VALVES OR VALVES Of L
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