ML20005E105
| ML20005E105 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/19/1989 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, TAC-49976, TAC-51606, TAC-53720, TAC-53942, TAC-55344, TAC-59402, TAC-64821, TAC-68046, TAC-68610, TAC-68834, TAC-69066, TAC-69693, TAC-69782, TAC-69978, TAC-71360, NUDOCS 9001030264 | |
| Download: ML20005E105 (17) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION s,
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December 19, 1989 Docket No. 50-395
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LICENSEE: South Caroline Electric & Gas Company FACILITY:
V. C. Sumer Nuclear Station, Unit No.1
SUBJECT:
SUMMARY
OF DECEMBER 12, 1989 MEETING WITH SOUTH CAROLINA ELECTRIC &
GAS COMP /SY General On December 12, 1989, representatives of the Office of Nuclear Reactor Regulation (NRR) met with representatives of the South Carolina Electric & Gas Company (SCE&G) to discuss the status of the licensing issues of the V. C. Sumer 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 meethig which presented the NRC's current assess-ment of the status of various licen:ing actions. This handout is included as. is a handout provided by the licensee which listed proposed technical specification changes needed for the next Refueling Outage, non-technical specification items of high priority, and other technical specifi-catiens changes previously submitted.
SCE&G indicated that they would not be pursuing the L amendment request for the March 1990 refueling outage. They intend to submit additional technical data to support its use for the refueling outage scheduled for the Fall 1991.
Because SCE&G is considering the replacement of the Sumer steam geperatnrs in a time frame earlier than that presented in their strategic plan, L is not consicered as important for the 1990 refueling outage. Thgy will sleeve the steam generator tubes for which they would have utilized L. SCE&G copmitted to providing a letter stating their request to delay the approval of L urtil the Fall 1991 refueling outage and to provide a schedule for submitting the additional information to complete the review.
SCE&G irdicated that, they would need to know by February 1,1990 whether F and the B&W sleeving amendments were likely to be approved by the NRC because they have to mobilire for these efforts and these mobilization efforts involve certain costs. This is also true for the RTD bypass nanifold amendment request.
The NRC also requested that SCE&G provide the staff information of how " indica-tion of cracking", which is stated in the Sumer Technical Specifications, is defined in the Summer procedures.
SCE&G indicated that with the refuelir.t cutage starting March 23, 1990, the surveillance interval for the B diesel generator expires prior to the beginning of the outage. Thereforc, they would need the approval of the amendment recuest b
$822 $8$M $$$8b P
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involving the removal of the 3.25 limit from technical specification 4.0.2 prior to March 15. SCE6G also indicated that they would provide information as to the critical date when they need to begin use of the biocide treatment.
The next meeting is currently scheduled for January 1990.
Original Signed By:
i John J. Hayes Jr., Project Manager Project Directorate 11 1 Division of Reactor Projects. 1/11 Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/encis:
See next page DISTalBUTION Docket <Atle NRC & LPDRs J. Sniezek 12/G/18 PD21 Rdg File E. Adensam J. Heyes OGC E.-Jordan MNBB.3302 ACRS(10)
H. Conrad 9/H/15 R. Borchardt 17/G/21 C. Y. Cheng 9/H/B B. Jones 8/E/23 t
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SUMMARY
/ SUMMER
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Mrs William A. Williams, Jr._
Mr. O. S. Bradham Technical Assistant - Nuclear Operations Vice President, Nuclear Operation Santee Cooper Nuclear Licensing P.O. Box 764(MailCode153)
Virgil C. Summer Nuclear Station Columbia, South Carolina 29218 P. O. Box 88 Jenkinsv111e, South Carolina 29065 J. B. Knotts, Jr., Esq.
Bishop. Cook, Purcell and Reynolds 1400 L Street, N.W.
Washington, D. C.
20005-3502 Resident Inspector /Sumer NPS c/o U.S. Nuclear Regulatory Comission Route 1 Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region 11 U.S. D clear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P. O. Box 293 Winnsboro, South Carolina 29180 Mr. Heyward G. Shealy, Chief i
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. Sumer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065
ATTENDANCE LIST FOR MEETING WITH SCE&G & NRC STAFF STATUS OF LICENSING ISSllES FOR V.C. SUMMER December 12, 1989 SCE&G NRC A. Koon, Jr.
E. Adensam K. Nettles H. Conrad J. Hayes 1
i i
.i STATUS OF NRC TACS FOR THE V. C. SUMMER PLANT December 12, 1989 49976 ISI PROGRAM (M. HUME)
-ITEM NOW GIVEN LOW PRIORITY.
51606 RV AND SV TESTING (ll.D.1) (GARY HAMER X-20919)
)
-SCE&G SUIMITTED RESPONSE TO STAFF COMENTS ON S/9/88.
1
-ADDITIONAL QUESTIONS SUPPLIED TO SCE&G AS A RESULT 1
0F THEIR S/9/88 RESPONSE.
-DRAFT OF SCE&G RESPONSES TO NRC QUESTIONS GIVEN TO j
HAMMER ON 7/25/88.
-CONFERENCE CALL HELD ON THE RESPONSES 8/10/88.
)
-SCE&G TRANSMITTED FOLLOWING INFORMATION IN DRAFT FORM:
i (1) DRAWING C-314-601 WEhT 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 COMENTS ON RESPONSE TO ITEM C OF SCE&G DRAFT RESPONSES.
-SCE8G PROVIDED RESPONSES TO NRC COMMENTS ON 5/31/89.
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 EGLG
-OPEN 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 INFOR!%L 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.
-GENERIC LETTER WILL PROVIDE GUIDANCE ON VENDOR INTERFACE, LICENSEE WILL BE REQUESTED TO CONFIRM BY LETTER THAN THEY MEE1 GL, AND NRC MAY INSPECT LICENSEE'S PROGRAM.
h 53942 ITEMS 4.2.3 & 4.2.4 0F GL 83-28, PREVENTIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS, LIFE TESTING & REPLACEMENT (C. MORRIS X-23284)
-BULLETIN IS BEINC PREPARED TO SEND TO CRGR.
55344 PROCEDURES GENERATION PACKAGES (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. TRAINING PROGRAM FOR UPGRADED E0Ps.
-SCE&G WAS TO RESPOND TO THE STAFF COMMENTS WHEN FURTHER STAFF GUIDANCE IS PROVIDED (SEE DELOW)..
l
-NUREG TO BE ISSUED 4/69 TO PROVIDE ADDITIONAL GUIDANCE ON PGPs.
-SEs TO BE WRITTEN Oh EACH PLANT WITH PLANT SPECIFIC COMMENTS ON THE PGPs. LICENSEE IS TO INCORPORATE THE COMMENTS OR MAINTAli A COPY OF THE JUSTIFICATION AS TO WHY THE COMMENTS WERE NOT INCORPORATEC.
-SUMMER SE TO BE ISSUED BY THE TECHNICAL BRANCH.
59402 40 YEAR OL LIFE AMENDMENT
-LICENSEE RESFONDED TO RAI 3/30/88.
-PM HELD MEETING WITH THE LICENSEE THE WEEK OF 4/18-4/21 TO DISCUSS THE ADDITIONAL INFORMATION REQUIRED TO EVALUATE THE AMENDMENT REQUEST.
-LETTER SENT TO LICENSEE REQUESTING ADDITIONAL INFORMATION 4/20/89.
i
-LICENSEE COMMITTED TO PROVIDING RESPONSE BY 6/19/89 IN 5/31/89 l
LETTER.
-LICENSEE RESPONSE TRANSMITTED 6/15/89.
i
-RE0 VEST FOR ADDITIONAL INFORMATION TRANSHITTED 8/16/89.
j
-LICENSEE TRANSMITTED A RESPONSE ON 9/1/89.
l l
64821 RSB 5-1, NATURAL CIRCULATION TEST OF THE REACTOR l
COOLANT
-REACTOR SYSTEMS BRANCH TO REVIEW THIS ITEM.
-CONFERENCE CALLS HELD 6/21/89, 7/19/89 AND 8/29/89.
-SCHEDULE FOR SUBMITTAL BY LICENSEE IS 12/89.
68046 IST 12/23/87 PROGRAM REVISION (K. DEMPSEY X-20918)
-SER ISSUED 4/19/88 l
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-SOME RELIEFS DENIED, SOME GRANTED
-LICENSEE MUST ADDRESS APPENDIX C OF THE TER WHICH COVERS OMISSIONS AND INCONSISTENCIES IN THE i
PROGRAM.
-MEETING HELD 6/1/88 TO DISCUSS RELIEFS WHICH WERE DENIED At012/23/87 REVISED PROGRAM.
l
-REVISED PROGRAM SUBMITTED BY SCE&G 8/31/88.
I
-ADDITIONAL INFORMATION REQUESTED VIA THE TELEPHONE ON 6/15/89 FOR EG&G TO COMPLETE THE REVIEW.
-PROCEDURE GTP 302 TRANSMITTED BY LICENSEE 7/19/89.
68610 IMPLEMENTATION OF STATION BLACK 0UT RULE, 10 CFR 50.63, A-22 (A. GILL)
-RESPONSE TRANSMITTED 4/17/89.
I
-REVISED RESPONSE TRANSMITTED BY SCE&G 10/2/89 68834 BULLETIN 88-05, NON-CONFORMING MATERI ALS SUPPLIED BY PIPING SUPPLIES, INC. AT FOLSOM, N.J. AND WEST JERSEY MANUFACTURING C0. AT WILLIAttSTOWN N. J.,
B-104
-RESPONSE SUBMITTED 9/13/88.
-WRITTEN RESPONSE DUE 60 DAYS AFTER COMPLETION OF ALL SCHEDULED ACTIONS.
-INSPECTION CONDL'CTED BY SCE8G 10/88.
-LICENSEE SENT LETTER ON RESULTS OF INSPECTION OF N0ZZLE PLATES ON 3/6/89.
69066 STEAM GENERATOR, L' (H. CONRAD)
-ENVIRONMENTA' 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 BEGIN UPON RECEIPT OF ADDITIONAL SCE8G INFORMATION.
-ADDITIONAL INFORMATION TRANSMITTED 6/13/89.
-MEETING HELD 10/5/89 WHERE IT WAS DETERMINED THAT ADDITIONAL INFORMATION IS REQUIRED TO DEMONSTRATE THE ADEQUACY OF THE USE OF EDDY CURRENT TESTING TO DETERMINE SG TUBE CRACK S12E AND ORIENT ATION.
-AWAITING INFORMATION.
1 69693 BULLETIN 88-08, THERMAL STRESSES IN PIPING l
CONNECTED TO REACTOR COOLANT SYSTEMS
]
l
-RESPONSE SUSitITTED 9/29/88.
-MEETING HELD 10/6/88.
l
1
-ADDITIORAL INFORMATION SUBMITTED BY SCE4G 12/19/B8.
-DIFFERENTIAL TEMPERATURE DATA SUBMITTED ON 3/23/89.
69782 GENERIC LETTER 88-17, " LOSS OF DECAY NEAT REMOYAL"
-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 SENT TO LICENSEE 6/26/89.
69978 BULLETIN 88-04, POTENTI AL SAFETY RELATED PUMP LOSS.
-FRITTEN RESPONSE DATED 7/8/88.
-RESPONSE ON EFW PUMPS PROVIDED 12/20/88.
-RESPONSE REQUIRED ON WHETHER INSTALLED MINIFLOW CAPACITY IS ADEQUATE FOR SINGLE PUMP OPERATIOE.
INFORMATION TO BE PROVIDED FOLLOWING 1990 REFUELING OUTAGE.
71360 NRC BULLETIN 88-10, "NON-CONFORMING MOLDED-CASED CIRCUIT BREAKERS".
-LETTER SENT TO SCE&G REQUESTING THAT INFORMATION BE PROVIDED AS IT EECOMES AVAILABLE.
-RESPONSE TRANSMITTED 3/31/B9.
-SUPPLEMENT 10F THE BULLETIN ISSUED 8/3/89.
-BY APPR0XIMATELY 11/10/89 LICENSEE MUST VERIFY PREVIOUS RESPONSE TO THE BULLETIN IN RESPONSE TO SUPPLEMENT 1.
l 71725 CENERIC LETTER 88-14, " INSTRUMENT AIR SUPPLY SYSTEM l
PROBLEMS AFFECTIhG SAFETY-RELATED EQUIPMENT"
-RESPONSE SENT 2/2/89.
1.
AFFECTED VALVES AND COMPONENTS TO BE ADDED TO THE PREVENTATIVE MAINTENANCE PROGRAM BY 4/23/89, l
2.
PERIODIC DEWPOINT MONITORING AND SYSTEM BLOWDOWN AT SELECTED LOCATIONS INITIATED BY 8/1/89.
3.
FULL IMPLEMENTATION OF A QUALITY RELATED PROGRAM FOR i
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.
1
i
-SUBMITTED RESPONSE TO 1.A 0F BULLETIN.
i
-LICENSEE INTENDS TO WORK WITHIN WDG.
i
-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 1.b 0F THE BULLETIN WITHIN 1 YEAR AS ORIGINALLY REQUIRED.
72893 FEEDWATER ISOLATION VALVES (TS 3.7.1.6)
-REQUEST SUBMITTED 4/5/89.
l
-SHOLLIED 5/3/89.
73300 SERVICE WATER SYSTEM B10 CIDE TREATMENT
-REQUEST FOR APPROVAL SUBMITTED 5/19/89.
-CONFERENCE CALL 9/18/89 REQUESTED BETZ SUBMITTAL TO EPA FOR REGISTRATION OF THE B10 CIDE AND THE EPA RESPONSE BACK TO THAT REQUEST.
-COPY OF STATE APPROVAL RECEIVED 11/14/89.
73713 GENERIC LETTER 89-06, " TASK ACTION PLAN ITEM 1.D.2 - SPDS".
I
-RESPONSE TRANSMITTED 7/7/89.
-LICENSEE TO TRANSMIT DESCRIPTION OF REVISED PROGRAM FOR OPERATION FOLLOWING MARCH 1990 REFUELING OUTAGE.
74068 GENERIC LETTER 89-13. " SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMENT".
-RESPONSE DUE BY 2/1/90 INDICATING THAT STEPS 1-5 0F 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".
-1NSPECTION OF CHECK VALVES DUE AT THE NEXT OUTAGE OF DURATICK GREATER THAN 4 WEEKS.
-RESULTS OF INSPECTION DUE WITHIN 60 DAYS OF THE COMPLETION OF THE INSPECTION.
-CLOSED OUT 10/27/89 74475 GENERIC LETTER 88-20, " INDIVIDUAL PLANT EXAMINATION FOR SEVERE ACCIDENT VULNERABILITY".
l l
-RESPONSE DUE DUE 60 DAYS FROM FEDERAL REGISTER NOTICE ON
i AVAILABILITY OF NUREG-1335.
-RESPONSE TRANSMITTED 10/31/89.
74538 GENERIC LETTER 89-21 " REQUEST FOR INFORMATION CONCERNING STATUS OF l
IMPLEMENTATION OF UNFESOLVED SAFETY ISSUES (USI) REQUIREMENTS"
-NPC DATA PROVIDED TO SCE8G ON 11/17/89 AT THE SITE.
-SCE&G TRANSMITTED RESPONSE TO GL ON 11/22/89.
f i
74559 RELIEF REQUEST ON MAIN STEAM DRAIN VALVES, ASME SECTION XI.
74577 F* EXTENSION (H. CONRAD X-20929)
-SHOLLIED 10/18/89.
-ADDITIONAL DATA TRANSMITTED 10/27/89.
74578 LOSS OF 0FFSITE POWER EVENT 7/11/89
-REQUEST FOR ADDITIONAL INFORMATION REQUESTED 9/6/89.
-ADDITIONAL INFORMATION TRANSMITTED BY SCE&G 11/9/89.
74735 GENERIC LETTER 89-07, "PCWER REACTOR %FEGUARDS CONTINGENCY PLANNIliG FOR SURFACE VEHICLE BOMBS".
l
-SUPPLEMENT 1 ISSUED 8/21/89.
-RESPONSE TO GL TRANSMITTED 10/30/89.
74821 RENLNBER!l4G 0F 3/4.7.11 l
74822 TS 3.7.1.5 MSIV MODES 2/3 74823 TS SR 4.8.1.1.2.C DG FUEL OIL SAMPLING, ANALYSIS, ETC.
74824 TS 3/4.5.2 REMOVAL OF RHR SYSTEM AUT0 CLOSURE INTERLOCK ( ACI),
-SHOLLIED 10/18/89.
-CONFERENCE CALL HELD 11/21/89.
-SCE&G TO PROVIDE CLARIFYING INFORMATION FIRST WEEK OF DECEMBER.
74825 TS 3.8.1 & 3.8.2 DG FUEL OIL STORAGE VOLUME
-)
e e
i 74826 TS TABLES 2.2-1 & 3.3-4, REPLACEMENT OF RTDs FOR RTD BYPASS MANIFOLD
-SHOLLIED 10/18/89.
-REQUEST FOR ADDITIONAL INFORMATION TRANSMITTED 12/7/89.
74839 TS 4.4.5.4 SG TUBE SLEEVES, B&W (H. CONRAD X-20929) 75004 GENERIC LETTER 8919,
- SAFETY IMPLICATIONS OF CONTROL SYSTEMS IN LWR NUCLEARPOWERPLANTS"(K.JABBOURX-21496)
-LICENSEE TO PROVIDE BY 3/20/90 SCHEDULE FOR IMPLEMENTING REC 0tt4ENDATIONS IN ENCLOSURE 2.
-C0ttilTMENTS MADE SHOULD BE IMPLEMENTED FRIOR TO STARTUP AFTER THE-FIRST REFUELING OUTAGE BEGINNING 9 MONTHS AFTER THE RECEIPT OF THE GL. (9/91 FOR SlNMER) 75049 TS OK DELETION OF CYCLE SPECIFIC PARAMETERS
-SHOLLIED 10/18/89.
-CONFERENCE CALL HELD 10/11/89.
-REVISED SUBMITTAL TRANSMITTED BY SCE&G 10/19/89.
75061 REQUALIFICATION SCHEDULE
-RESPONSE PROVIDED 8/18/89 TO GL 89-12 *0PERATOR LICENSING EXAt11 NATIONS WHICH REQUESTED AN EXTENSION TO THE ANNUAL TRAINING CYCLE.
-LETTER TRANSMITTED TO SCE&G 10/26/89 INQ'JIRING AS TO WHETHER AN EXEVPTION WAS REQUESTED AND/0R A CHANGE IN PROGRAM CYCLE.
-LICENSEE'S 11/9/89 RESPONSE RE0 VESTED 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 75360 TS 4.7.15, MSIV STROKE TIME TEST 75361 TS 4.0.2, 3.25 SURVEILLANCE TIME LIMIT l
?????
BULLETIN 87-02, SUPPLEMENT 1 " FASTENERS TESTING TO DETERMINE CONFORMANCE APPLICABLE MATERIAL SPECIFICATIONS"
-RESPONSE SUBMITTED 7/20/88.
?????
EULLETIN 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 EE TAKEN:
1.
INTERMEDIATE FUEL ASSEMBLY CONFIGURATIONS HAVE BEEN IDENTIFIED AND EVALUATED TO ASSURE A BORON CONCENTRATION TO ASSURE A MINIMUM SHUTDOWN MARGIN OF St.
2.
ASSURE THAT FUEL LOADING PROCEDURES ONLY ALLOW INTERMEDIATE FUEL ASSEMBLY CONFIGURATIONS WHICH DO NOT VIOLATE ALLOWAELE SHUTDOWN MARGIN AND THAT THESE PROCEDURES ARE STRICTLY ADHERED TO.
3.
ASSURE THAT STAFF RESPONSIBLE FOR REFUELING OPERATIONS ARE TRAINED IN PROCEDURES NOTED IN ITEM 2 ABOVE.
TACS CLOSED E&
DESCRIPTION OF THE TAC DATE CLOSED 51287 SPOS 07/17/89
.53406 AUTO SHUNT TRIP TS, GL 83-28 ITEM 4.3 06/06/89 54030 ITEMS 4.5.2 t. 4.5.3 0F GL 83-28, 06/12/89 REACTOR TRIP SYSTEM FUNCTIONAL TESTING, ALTERNATIVES & TEST INTERVALS 59451 DIESEL GENERATORS TS 05/30/89 56935 RCP TRIP CRITERIA, GL 83-10D 03/15/89 62803 CONTAINMENT STRUCTURAL INTEGRITY 04/28/89 65060 REMOVAL OF FIRE PROTECTION REQUIREMENTS 07/24/89 FROMTHETS(GL86-10) 65778 REMOVAL OF ORGANIZATIONA!. CHARTS FROM 07/24/89 THE TS l
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, 67340 ORGANIZATIONAL CHARTS TO REFLECT 07/24/89 1/25/88 FEORGANIZATION 67811 VANTAGE 5 FUEL, SPENT FUEL STORAGE.
10/28/88 l
l
i t
I 67812 ISI RELIEF, HYDROSTATIC TESTING OF THE 06/22/89 I
SGB SYSTEM J
68045 SINGLE CELL CHARGING OF SAFETY RELATED 04/03/89 BATTERIES.
68274 SG TUBE SLEEVING.
11/10/88 68644 VANTAGE 5 FUEL, REMAINING TS SECTIONS.
10/28/88
~
68956 BORIC ACID CORROSION OF C-STEEL 10/06/88 COMPONENTS IN PWR PLANTS GL 88-05.
71554 GENERIC LETTER 88-11, *NRC POSITION ON 02/07/89 RADIATION EMBRITTLEMENT OF REACTOR VESSEL MATERIALS AND ITS IMPACT ON PLANT OPERATIONS".
72685 BULLETIN 88-09, " THIMBLE TUBE THINNING 01/04/89 IN WESTINGHOUSE REACTORS".
72727 AMENDMENT ON DC SOURCES (TS 3/4.8.2) 08/07/89 73209 FAILURE OF WESTINGHOUSE STEAM GENERATOR 09/18/89 TUBE MECHANICAL PLUGS (BULLETIN 8e.o 73301 TS 4.0.3 AND 4.0.4 AMENDMENT. 08/08/89 73548 CENERIC LETTER 89-08, 07/20/89 " EROSION / CORROSION INDUCED PIPE WI,LL THINNING" 73941 BULLETIN 88-03, INADEQUATE LATCH 02/06/89 ENGAGEMENT IN HTA TYPE LATCHING RELAYS MANUFACTURED BY GE.
i' .e Technical Specification Items Needed for Refuel V p Steam,ggnerator F# Renewal This proposed change allows the use of the F# criteria for the life of the steam generators. Steam Generator Sleeving i This proposed. change allows the use of a B&W designed "short sleeve." RTD Bypass Elimination This proposed change permits the removal of the RTS bypass manifolds from the reactor coolant system. Removal of RHR System Autoclosure Interlocks This proposed change allows for the elimination of the protective interlocks which close the RHR suction isolation valves on high pressure. Removal of Cycle Specific Parameters from Techical Specifications This proposed change removes cycle specific parameters from the Technical Specifications which will be controlled by the Licensee. Part of this change includes the repositioning of control rods to address control rod wear. Generic Letter 89-14, " Removal of the 3.25 Limit on Extending Surveillance Intervals" This change deletes 3.25 limit on extending surveillance intervals. RHR Sump Level Instrumentation This proposed change provides different level instrumentation ' for EQ purposes. NOTE: The refueling outage is scheduled to commence on March 23, 1989. In support of the outage, these changes need to be approved by February 1, 1990.
al'. ;.
- g,
'i '[ + 'Non Technical Specification Items of High Priority i: 40 Tear OL It is requested that this change'be._ approved by December 31, 1989. Service Water System Blocide Treatms..c It is. requested that this change be approved by December'31, 1989. l ': ?'r I (- k i' l 1 .. L
n O Status of Other Technical Specification Changes Previousiv Submitted Steam Generator L' SCE&G intends to continue developing supporting information for L* however, not for Refuel V. It is expected that this supporting information will be provided by July 1, 1990. We request that this item be approved by July 1, 1991. Main Steam Isolation Valve Stroke Time This change revises the required stroke tire from 5 seconds to 7 seconds. It is requested that this change be approved by June 1, 1990. Feedwater Isolation Valves This change will be returned to SCE&G because the change is not plant specific. Renumbering of Tech Spec 3.7.11 This change has been resubmitted at of December 11, 1989, at the request of the NRC for reformatting purposes. It is requested that this change be approved by June 1, 1990. Main Steam Isolation Valves This change will be returned to SCE&G because the change is not plant specific. Diesel Generator Fuel Oil Sampling This change needs to be resubmitted per the request of the NRC for reformatting. This will be submitted by January 19, 1990. It is requested that this change be approved by July 1, 1990. Diesel General Fuel Oil Storage Volume This change has been resubmitted as of December 11, 1989, at the request of the NRC for reformatting purposes. It is requested that this change be approved by July 1, 1990.
r;7 L 2 L involving the removal of the 3.25 limit from technical specification 4.0.2 prior to March 15. SCE&G also indicated that they would provide information as to the critical date when they need to begin use of the biocide treatment. The next meeting is currently scheduled for January 1990, i-k )f dw (f. r ' ') "/ hu J. Hayes Jr., Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/encis: l See next page i i i}}