ML20147E075

Summary of 880217 Meeting W/Util in Rockville,Md Re Status of Current & Future Licensing Actions for Facility.Attendees List,Agenda & Handouts Encl

ML20147E075
Person / Time
Site:	Summer
Issue date:	02/29/1988
From:	Hayes J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8803040260
Download: ML20147E075 (32)

Text

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FEB 2 9 mt Docket No. 50-395 DISTRIBUTION:

See attached sheet LICENSEE: South Carolina Electric and Gas Company FACILITY: V. C. Sumer Nuclear Station

SUMMARY

OF MEETING ON FEBRUARY 17,~1988 WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY GENERAL On February 17, 1988, the NRC staff met with representatives of the South-Carolina Electric and Gas Company (SCE&G) to discuss the status of current and future ' licensing actions for the V. C. Sumer Station. The meeting was held at the NRC headquarters in Rockville, Maryland. A list of those persons who attended the meeting is included as Enclosure 1.

DISCUSSION The agenda for the meeting is included as Enclosure 2. Handouts _provided at .

the meeting are included as Enclosures 3-5. Major items of importance discussed included:

1. The utilization of Westinghouse Vantage 5 fuel for the next and subsequent reloads and the ability of the NRC to review the licensee's submittals in a timely manner to meet the scheduled restart after the October 1988 refueling outage.

2. The need to complete those licensing issues which are 5 years old or older.

3. Technical Specification changes needed for the restart after the refueling outage. ,

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John J. Hayes, Jr., Project Manager Project Directorate II-I Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page 8803040260 880229 PDR ADOCK 05000395 P PDR

• SEE PREVIOUS CONCURRENCE

• LA:PD21:DRPR

• PM:PD21:DRPR D.f 1:DRPR PAnderson JHayes EAdensam 2 /25 /88  ?/ 24'88 /g//88

Docket No. 50-395 DISTRIBUTION:

See attached sheet LICENSEE: South Carolina Electric and Gas Company FACILITY: V. C. Summer Nuclear Station

SUMMARY

OF MEETING ON FEBRUARY 17, 1988 WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY GENERAL On February 17, 1988, the NRC staff met with representatives of the South Carolina Electric and Gas Company (SCE&G) to discuss the status of current and future licensing actions for the V. C. Summer Station. The meeting was held at the NRC headquarters in Rockville, Maryland. A list of those persons who attended the meeting is included as Enclosure 1.

DISCUSSION The agenda for the meeting is included as Enclosure 2. Handouts provided at the meeting are included as Enclosures 3-5. Major items of importance discussed included:

1. The utilization of Westinghouse Vantage 5 fuel for the next and subsequent reloads and the ability of the NRC to review the licensee's submittals in a timely manner to meet the scheduled  !

restart after the October 1988 refueling outage. j

2. The need to complete those licensing issues which are 5 years old or older. i l

3. Technical Specification changes needed for the restart before and i after the refueling outage.

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

Enclosures:

I As stated cc: See next page LA[Q2[QR PM:PD21:DRPR D:PD21:DRPR PA;nderso(n{R JHa es EAdensam l

z/ A'/88 J/, /88 / /88

Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C. Sumer Nuclear Station

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.

Bishop, Libeman, Cook, Purcell i and Feynolds  !

1200 17th Street, N.W.

Washington, D. C. 20036  ;

i Resident Inspector /Sumer NPS i c/o U.S. Nuclear Regulatory Comission Route 1, Box 64 l Jenkinsv111e, South Carolina 29065 l Regional Administrator, Region II U.S. Nuclear Regulatory Comission. l 101 Marietta Street, N.W., Suite 2900  !

Atlanta, Georgia 30323

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Chairman, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 29180 j

Attorney General l Box 11549 l Columbia, South Carolina 29211 j Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 ,

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ENCLOSURE 1 l a

ATTENDANCE FEBRUARY 17,1988 MEETING i.

EGEk@ NBG  !

M. Williams E. Adensam A. Koon J. Hayes l D. Warner R. Jones * ,

D. Fieno* l W. Brooks * ,

E. Branagan*

G. Lainas* 1

• Parttime attendance l

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.- Ell CLOSURE 2 AGENDA NRC MEETING WITH SCE&G FEBRUARY 17, 1988 WEDNESDAY.0 FEBRUARY 017.1988

1. PLANT OPERATING STATUS AND ORGANIZATIONAL 8:00A CHANGES

2. DISCUSSION ON VANTAGE V FUEL 8:30A  !

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3. STATUS OF LICENSING ACTIONS 9:00A l I

4. TECHNICAL SPECIFICATION CHANGES IN 9:30A l PROGRESS /OTHER LICENSING ACTIONS

5. FUTURE VISIT TO OPERATIONS CENTER /IPE 10:00A GENERIC LETTER

6. MEET WITH GUS LAINAS 10:30A

7. REMAINING ISSUES 11:00A  ;

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. ENCLOSURE 3 STATUS OF NRC TACS FOR THE V. C. SUMMER PLANT 49976 ISI/IST0 PROGRAMS IST (KEN DEMPSEY)

-SER TO BE ISSUED DURING 2/88

-SOME RELIEFS DENIED, SOME GRANTED

-LICENSEE MUST ADDRESS APPENDIX C OF THE TER WHICH COVERS OMISSIONS AND INCONSISTENCIES IN THE PROGRAM.

ISI ( )

-REVIERER NEEDS TO PUSH SER 51137 RG01.970 INSTRUMENTATION

-SER ISSUED

-THREE OPEN ITEMS

- ONE FOR STAFF ACTION

-generic review of the need for Cat 2 EQ instrumentation to monitor accumulator pressure and temperature.

- TWO FOR SCE&G ACTION (MORE INFORMATION)

-install instrumentation to monitor containment temperature between 40-400 F or provide an analysis justifying the use of the 50-350 F instrumentation. ,

-have operational EQ instrumentation to '

monitor SG SRVs and ADVs releases.

51287 SEDS

-SER ISSUED

-THREE OPEN ITEMS

1. TOP LEVEL ICONICS ARE NOT CONTINUOUSLY DISPLAYED.

2.

a. SYSTEM RESPONSE TO OPERATOR COMMANDS IS VERY SLOW.

b. SYSTEM HAS NOT BEEN ABLE TO MEET ITS i UNAVAILABILITY GOAL OF LESS THAN 1 %. I

c. LACK OF REDUNDANCY IN THA DATA ACQUISITION CONTROLLER AND THE UNIBAR l

CONTROL SWITCH INCREASES THE VULNERABILITY OF THE SYSTEM TO FAILURES CAUSED BY THESE COMPONENTS.

3. HUMAN FACTOR PRINCIPALS NEED TO BE RESOLVED.

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4. SOME NON-VALID VALUES OR CONDITIONAL FLAGS ,

EXISTED FOR RHR FLOW RATE, SUBCOOLING i MARGIN, REACTOR VESSEL LEVEL INDICATTION SYSTEM (RVLIS), STARTUP RATE, CONTAINMENT HYDROGEN, AND SAFETY INJECTION (SI) FLOW.

51606 RVOANDOSV0 TESTING (II.D.1)

-SCE&G OWES STAFF RESPONSE

-ANTICIPATED RESPONSE DATE WAS 12/87 53406 AUTOOSHUNTOTRIPOTS 0GLO83-280 ITEM 4.3

-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 UNDERVOLTAGE TRIP, 53720 ITEM 02.200FOGLO83-28.0 EQUIP.0CLASSIFICATIONOAND VENDOR 0 INTERFACE 0FOROSAFETYORELATED0 COMPONENTS ,

1

-FARLEY TO BE HANDLED AS THE LEAD PLANT

-TER ISSUED BY EG&G

-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.

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

53942 ITEMSO4.2.30&O4.2.400FOGLO83-28.0 PREVENTIVE MAINTENANCE 0 PROGRAM FORORXOTRIP0 BREAKERS.0 LIFE T_ESTINGO&0 REPLACEMENT

-SOME ACTION NEEDS TO BE TAKEN ON THIS TAC 54030 ITEMSO4.5.20&O4.5.300FOGLO83-28.0 REACTOR 0 TRIP SYSTEM 0 FUNCTIONAL TESTING.0 ALTERNATIVES 0&OTEST INTERVALS

-SOME ACTION NEEDS TO BE TAKEN ON THIS TAC 55344 PROCEDURES 0 GENERATION 0 PACKAGES 0(SUPPLEMENT 01.

NUREG-00737)

-DRAFT SE ISSUED 6/29/87

-PROBLEMS IDENTIFIED INCLUDED:

1. PLANT SPECIFIC TECHNICAL GUIDELINES

2. WRITERS GUIDE

3. PROGRAM USED FOR VALIDATION OF EOPs

4. TRAINING PROGRAM FOR UPGRADED EOPs

-SCE&G OWES RESPONSE TO THE STAFF COMMENTS 56169 THIOACTIONOITEMOI.D.1.2.0DETAILEDOCONTROLOROOM DESIGNOREVIEWO

SUMMARY

OREPORT

-NEGATIVE SER ISSUED

-NEW REPORT ISSUED BY LICENSEE 5/28/87???

I 56935 RCPOTRIP0 CRITERIA.0GLO83-10D

-STATrJS UNKNOWN

-REVIEWER NEEDS TO BE FOUND 59146 10CFR50.6200PERATINGOREACTORSOREVIEWOATWS

-SCE&G NEEDS TO SUBMIT METHOD TO IMPLEMENT THIS REQUIREMENT

-SUBMITTAL SHOULD ALLOW ADEQUATE TIME FOR IMPLEMENTATION DURING 10/88 REFUELING OUTAGE .

-STAFF WILL DOCUMENT THE NEED FOR THIS INFORMATION I IN A LETTER TO NAUMAN THE WEEK OF 2/15/88 59402 400 YEAR 00LOLIFE0 AMENDMENT <

-SCE&G OWES STAFF RESPONSE I

59451 DIESEL 0 GENERATORS 0TS

-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  ;

62803 CONTAINMENT 0STRUCTUREGINTEGRITY

-RAI TO BE SENT TO SCE&G WEEK OF 2/15/88 l

-MEETING TO BE SCHEDULE FOR MARCH 1988 64558 RB0 COOLING 0 SYSTEM

-AMENDMENT PACKAGE READY

-AWAITING REQUEST FROM SCE&G 648219 RSB05-1.0 NATURAL 0 CIRCULATION 0TESTOOFOTHE0 REACTOR COOLANT 1

-CHECK AS WHO HAS THIS ITEM IN THE NEW ORGANIZATION

-SCE&G MUST MEET LICENSEE CONDITION I

650609 REMOVAL 00F0 FIRE 0 PROTECTION 0REQUIREMENTSOFROMOTHEOTS

a GLO86-10

-RE-SHOLLY TO BE ISSUED 2/17/88 65321@ PHYSICAL 0 SECURITY 0 PLAN

-SE FROM NMSS RECEIVED 2/12/88

-SE TO BE ISSUED 2/88 65778@ REMOVAL 00F0 ORGANIZATIONAL 0CHARTSOFROMOTHEOTS

-HARRIS, WHICH WAS THE LEAD PLANT, HAD IT SE ISSUED

-SCE&G OWES INPUT BASED UPON HARRIS SE 65779@ FISSION 0 CHAMBER 0 DETECTORS

-REGION II REVIEWING 66258 LOSS 00FORHROWHILEORCSOPARTIALLYOFILLED.01/20 LOOP OPERATION

-COPIES OF SCE&G SUBMITTAL SENT TO LEAD PM AND LEAD '

REVIEWER.

67077 SERVICE 0WATEROPUMPOROOMOTEMPERATURE0 MONITORING $IS 3.7.1.1

-SHOLLEY NOTICE TO BE ISSUED 2/17/88 l

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E!. CLOSURE 4 SCE&G/NRC PROJECT MEETING FEBRUARY 17,1988 Meeting

Purpose:

Periodic Review of Licensing items SCE&G Attendees: Mike Williams, General Manager, Nuclear Services Al Koon, Manager, Nuclear Licensing Doug Warner, Manager, Core Engineering &

Nuclear Computer Services NRC Attendees: Jack Hayes Elinor G. Adensam Gus Lainas Wade Hodges Meeting Location: NM Headquarters i Meeting Time: 8:00 A.M.

Agenda items:

• Plant Operating Status e Technical Specification Changes In Progress e Vantage V Technical Specification Changes e Vice President Nuclear Operations Absence for March, April,1988 e IPE Generic Letter l e SCE&G Nuclear Operations Division Organization Changes e Meet with Mr. Lainas at 10:30 e Discuss Future Visit To Operations Center e Other Licensing items 4

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j Sheet 1 of 8 February 16,1988 LICE N5tNG ITE M5 STATUS LIST V. C. 5UMME R NUCLE AR ST ATION TE(HNICAL $PEOf 4 CATION REVI510NS $U8MITTED TO NRR TECHNICAL FEDERAL liiLE SU8MITTAL REGISTER NRR APPROVAL SPEOFICATION SCE 8G REV153ONSROBLE M NRR TECHNICAL DATE DATE(5) 155UANCE

'** REQUIRE D NRR TAC. NO. STATUS (Estemated MANAGE R) DATE Date) Date) 3/4 8 " AC Sour (es" Revises the Techngal 5petaf e(ation to combene 06-10-85 07-17-85 Remaining TS Parteal TS (RJ8) testmg to redute thermal tranuents. thange 18 12-06-85 Emp 08-16-85 Request under request 59451 months survestarxe to refuehng. (hange loadeng review 01-30-86 approved limits to loading bands, and other (larifying 06-04-86 05-30-86 (hanges Emp 07-04-86 NRC(omments to be aesolved 1st Qtr. e8 3616 ~Contamment Tech Spec revised to change the numbes/ sample 09-16 86 11-05-86 4th Refuelang (RJB) Structural of tendons to be tested. deleted speofec tables. 08-18 87 Emp 12-05-86 Integr sty" and revesed the menemum required average Need to tendon force for each group respond 62803 additional NRC Questions 3 3-2 "Reactor Trip Te(hnmal speofecation to be reves=d e optimize 12 08 83 05-06-87 SE R being Tbl4 3-1 System reactor trip break er testing Emp 05-05 87 written (HID) Surveillan(e Requirements

• 53406 4 6 2.3 a 2 ~ Reactor Bldg Revise Te(h. Spec. to require less than 2000 gpm 01 20 87 02-26 87 SER Approved On Hold 4th Refueling (HID) Coohng System" to RBCU's 02-24 87 Esp 03 28 87 (Giardma) (Awaiting SCE&G release 64458 request) 60 NSRC Revise Tech Spec.tochange Management 02 10 87 (J58) Overpte of the NSRC.

Sheet 2 of 8 February 15,1988 LICE NSING 11E M5 5TATUS LIST V. C. 5UMME R NUCLE AR $ T ATION TECHNIC AL SPECIFICAT6ON RE VISIONS SUBMITTF D TO NRR F E DE RAL TECHNICAL NRR APPROVAL TITLE SUBMaiTAL REGISTER SPECIFICATION SCE &G NRR TECHNICAL DATE REVi$lON/PROBLE M DATE(5) ISSUANCE REQUIRED p$gg * *

• NRR TAC. NO. STATUS (Estimated DATE MANR)

Date) 3337 "Fere Detection Evaluate removing all Fire Protection from Tech. 03-31-87 07-29 87 (03-04-88)

System" Spec. and address en separate document (F5AR) 12-21-87 3791 "Fsee Supptession System" 3792 ~5 pray and/or Sprmkles Systems" 3793 "CO2 System" 3794 "Fire Hose Station" 3795 "Yard Fire Hydrants and Hose Stations" 3 7.10 "Fire Rated (HtD) Assemblies" 65060 Figures 6 2 & Organaatsonal Revese Tech Spec to delete organsratw>nalcharts 0746-87 (0) 04 88) 64 and Trammg and revise t,anning requnements 12-31 87 (HID) Changes 014688 (R)8) 65778 Table 4.3-1 "Reattor Trep Revise table notatH>n to seflect that detector 07-07 87 (05-30-88)

(RJ8) System Inst. 5urv plateau curves are nolonger appistable.

Requerements" 65779

Sheet 3 of 8 February 16,1988 LKE N$tNG ITE M5 5TATUS LIST

v. C. 5UMMER NUCLEAR 5TATION TE CPNICAL $PECIFICATION RE VISIONS $USMITTE D 10 NRR F E DE RAL TECHNICAL I LE NRR APPROVAL

$UBMIT T AL REGl5T E R l SPE CIF6 CATION NRR TECHNICAL DATE REVISION /PROBLE M DATE(5) ISSUANCE M5UE stimated NRR TAC NO STATUS (Estimated MANAGE R)

Date)

Date)

Tb! 3 7-74 Area Temperature Revise temperature for SW pump /ureen room. 12-22-87 (AMM) Monstormg

Sheet 4 of 8 February 16,1988 LICEN58NG ITEM 5 5TATUS LIST V. C. 50MMER NUCLEAR $TATION TECHNICAL SPTCIFICATION REVISIONS TO fi Sv8MITTED IST OVARTER 1988 TECHNICAL F E DE RAL TITLE SUBMITTAL NRR APPROVAL SPECIFICATION REGIS TER SCEgG REVISION!PROBL E M NRR TECHNICAL DAT E DATE{$) ISSUANCE REQUIRE D NRR TAC NO '

• MANAGE R) STATUS (Estimated DATE Date) Date}

3/4 4 5 ~5 team Revise recent Techne (al 5pecification change to (DWI) Generator" (orrett paragraph numbers (Admenestrative Change) 30 1CO and lawotporate standard T5 LCO and Surwenitarxe 40 Surveillarxe requirements (GL 87-09)

(*4DS) RQuerements 3/432 ESFAS Revese Table 3 3 5 tochange notes to reisted to (AMM) instrumentatson St response tea:es CVC5 vatwes.

3912 VANTAGE-5 Revise Techne (alipecifscatw>n to support 53&56 VAN TAGE-5 Fuel aueptarwe (AMM)

Sheet 5 of 8 February 16,1988 LICE N5tNG ITEM 5 5TATUS Lisi V. C.5UMMER NUCLE AR 5TAf 8ON TE(HNN'At SPEOfl(ATiON RE VISIONS TO BE SUBMITTE0 2ND OUARTER 1988 TE CHNICAL F E DE RAL TITLE NRR APPROVAL SPEOfiCATION SUBMITTAL REGl5TER SCE&G RE vt$10NPROBL E M NRR T E CHNIC AL DATE (155UE DATE(5) ISSUANCE REQUIRED NRR TAC NO REVIEW (Estimated STATUS (Estamated DATE MANAGE R)

Date) Date) s81.12 0.esel Fuel O.I Change to Standard Tech Spec. Requerements (DCB) Analyses 332 *E5F Need to revise Spec. to implement Westmghouse Well need NRC (CJM) Instrumentation

• Ownefs Group optimization programs. anput on 3 3.1 review prior to submittal 3842 MOV Thermal Delete surveillarge requerements for thermal (RJ8) Overload overloads that are contmuously bypassed Add Protection and valves to lest and tor rect typos Bypass Devnes 311 Shutdown Margm Delete / revise 41 1 1 a and address shutdown (15 8) masgin in 3131 -

3421 "Safety Valves

• Revise T5 to accommodate testmg of Press, and 3422 MA safety valves an plate.

371.1 (MDS)

(1) 331 *RPS Need to revese Spec to smplement Westmghouse To be split into (CJM) Instrumentation" Owners Group optamaration program two submittais 4712 Emergen(y Corre(t P51G hstings (15 8) Feedwater Pump (To be VAN TAGE-5 Changes ne(essary to support 4th refuel determined) 4th Hef uel (AMM)

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Sheet 6 cf 8 Februiry 16,1988 LICE N5tf(s lT E MS $ T ATUS LIST V C SUMMER NUCLEAR 5TATION T E C HNI( At $PE CIFl( ATION RE Vi$lONS TO 8E SU8MITTED 3RDQUARTER 1988 TECHNICAL FEDERAL TITLE NRR APPROVAL SUBMITTAL RE GIST E R SCE &G SPEOFICAT60N NRR TECHNICAL DATE RE VISION /PROBL E M DATE(5) ISSUANCE REQUIRED NRR TAC NO '*'

STATUS (Estemated DATE MANAGE R) Datc)

Date)

AMSAC AMSAC Provide plant speof ac AMSAC Desagn (Awaiteng 1st Qtt~88 (MDB) NRC request to auelerate submsttal )

Sheet 7 of 3 February 16,1988 ItCE N$1NG IT E Ms S TATUS t l5T V C $UMMER NUCLE AR 5f Al4ON TE(HNICAL $PECIFICATION REVSON$

TO BE $UBMITTE D 4TH QUARTER 1988 FEDERAL TITLE $U8MIT TAL RE Gl5T E R $C[gG

$PECIFICATION NRR TECHNICAL DATE RE Vi$10NPROBLE M DATE($) 1550ANCE REQUtRED NRR TAC NO

• STATU$ (Estimated DATE MANAGE R) Date)

Date) 381.1 ~ AC Sourt es* E oatuate addeesung Loed Sequeruer en a (RJB) separate speofocation (Need NRR answer to prevKnas submittal for 3/4 8 )

Sheet 8 of 8 *

• February 16,1988 LICEN51NG ITE M5 5TATU5 LIST V C.5UMMER NUCLEAR $TATION OTPER TECHNICAL REVIEWS TO BE SU8MITTf D 1988 F E DE RAL DE SCRIPTION ACTUAL liEM(ISSUE REGISTE R ESTIMATED NRR TECHNICAL SCE8G DATE MANAGE R) SU8MITTAL DATE NRR TAC. NO REVIEW (Estimated DATE($) (E stsmated DATE Date)

GL 82-33 (197) Request for addstsonal enformation on Reg ist Qtr '88 (AMM) Guede 197 emplementation.

CR HA8 Report Control Room Hatutatuisty Report Response 1st Qtr ~88 (AMM)

GL 83-28 Resolve NRC Questsons on Generst letter 2nd Qtr. '88 (15 8) 83-28 (ATW5)

EOP-GP E OP - Generateon Pac k age, resolve N RC 2nd Qtr . *88 (MD8) com nents 40 Year O L E atends O L to 40 years from date of assuance 4th Qtr. '87 08-02 85 0547-86 '

(AMM) Prowde supplemental Emp 06 06-86 i

59402 information as requested (0) 0731, item Response to NRC Staf f questions (letter dated 4th Qtr. '87 II D 1 7-1-85) pertaining to relief and safety valves (AMM) These questsons ere m (onjunction with NUREG 073 7, item il D I 51606

Notes to Licensing Items Status List (1) To be split into two submittals based on NRC recommendations. LaBorde to rework.

(2) Perform feasibility study with lead Engieer (R. Clary to assign) to determine if revision should be accomplished.

(3) Report received - All that is needed to attach cover letter and submit to NRC after Nuclear Engineering concurs.

(4) AM preparing final response letter.

(5) Deleted (6) Deleted (7) Deleted (8) Deleted

• Previous submittals covered by TS appeal meeting (CGSS-6861, June 2, 1982)

NOTE: Next regularly scheduled NSRC Meeting will be on 3888.

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L N U C A F U R 5 N T O E R D T G E A A M O T L N M E A

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SUMMER PLANT PARAMETERS j

• Original Current Future No.of Loops 3 3 3 Fuel Type 17x17 STD 17x17 STD Vantage 5 ,

i Reactor Power, MWt 2775 2775 2775 '

Thermal Design Flow, gpm/ loop 98,000 96,200 92,600 Expected Tube Plugging Limit ~4 ~16 ~15

] Core Bypass Flow, % 6.4 6.4 8.9 Reactor Coolant Pressure, psia 2250 2250 2250 Reactor Coolant Temperature,'F e Core Average 591.2 590.5 l

e Vessel Outlet 618.7 618.7 e Zero Load 557 557 l

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VANTAGE 5 FUEL -

Features Benefits

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1. Blankets improved Neutron Utilization i

i 2. Integral Fuel Burnable Absorber (IFBA) Power Peaking and MTC Control with l Reduced Fuel Component Handling 3 3. Intermediate Flow Mixer (IFM) Grids increased DNBR Margins l 4. Reconstitutable Top Nozzle Allow rod removal / replacement and l assembly reconstitiution l S. Extended Burnup Lead Rod Average Burnup of Up to 60000 MWD /MTU l

l WCAP-10444, Reference Core Report - Vantage 5 l Fuel Assembly, December 1983

1 I LEAD VANTAGE 5 TRANSITION PLANTS

! Plants . Status Callaway 1 NRC SER issued l

Virgil C. Summer Cycle 5 Transition I

l Shearon Harris 89 Submittal l

Diablo Canyon 89 Submittal l

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! OBJECTIVES .

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) o Specify Plant Baseline Parameters To Enhance Future Design and Operation Flexibility .

o Establish New Licensing Baseline With Vantage 5 Fuel i

j e Core Physics ,

I e Core Thermal- Hydraulics

e Safety Analyses I e Fuel Storage l 0 License The Vantage 5 '3aseline For Future Cycles i

) o Design Cycle 5 Within The Bounds Of The New Vantage 5 Licensing l Basis I

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_ = = - , . -w . v

OUTPUTS Item Scope Rack Criticality Report e Analyses justifying storage of <4.25 w/o 17 x 17 OFA and STD fuel in existing fresh and spent fuel racks j with credit for burnup taken e Technical Specification changes to l

revise BU dependent exposure limits j

for regions 2 and 3 (no physical

changes)

Vantage 5 Transition e Mechancial Design Licensing Submittal e Nuclear Design o Thermal and Hydraulic Design e Accident Evaluations e Technical Specifications Cycle 5 Reload Safety Evaluation

• WCAP-9272 Scope Per 10CFR 50.59 FSAR Updates e Chapters 4,6, and 15 i

Peaking Factor Limit Report e Cycle Dependent Power Factors to l

i support Hot Channel Fo Surveillance l: e BU Dependent AFD Limits

+w 4-u. e A.Ah _ +._ -_ . _ e---m .- --a_ - --.-+-m . .- 4 . c .A ,, hi -- m- S_ e _ s m - - -

i NUCLEAR DESIGN

~

Equilibrium

Current Cycle 5 Cycle 4

Cycle Length 18 mo. 18 mo. 18 mo.

Maximum Enrichment 3.85 w/o 4.2 w/o 4.2 w/o Fo 2.25 2.45 2.55 FAH 1.55 1.62 1.68 .

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i MTC $0 pcm/*F at HZP ~3 pcm/*F at HZP ~3 pcm/*F at HZP

$0 pcm/*F at HFP $0 pcm/*F at HFP I Control Strategy CAOC RAOC With Base RAOC With Base Load Option Load Option i

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CORE THERMAL AND HYDRAULIC DESIGN

Current Cycle 5 -

Key DNBR Parameters i l e Power, MWt 2775 2775

) e Pressure, psia 2250 2250

e Flow, gpm/ loop 98000 92600 i e Tin,*F 556. 552.3 e Fan 1.55 1.62 e Core Bypass Flow, % 6.4 8.9 I

DNB Correlations

• W-3 WRB-1 (STD Fuel)

WRB-2 (Vantage 5 Fuel)

Thermal Design Procedure

• Standard improved Thermal Design i

Procedure (ITDP) '

Cor,sistent with W Topical; "Reference Core Report Vantage 5 Fuel Assembly",

WCAP-10444, December 1983.

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ACCIDENT EVALUATIONS

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1. Perform Specific Analyses For  ;

a

e Large Break LOCA .(Using BASH *) ,

) e Small Break LOCA (Using NOTRUMP*)

I e All Fuel Related Non-LOCA i Accidents j  !

2. Justify Continued Applicability of Current

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• Dose Analyses ,

o Containement P/T Analyses i

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) Latest NRC Approved Codes / Methods to be used in LOCA Analyses i

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1 AFFECTED TECHNICAL SPECIFICATIONS SECTION DESCRIPTION COMMENT 2.1.1 Reactor Core Safety Limits New Core Limits for Vantage 5 Fuel with the improved Thermal Design Piocedure and FAH = 1.62 '

2.2.1 Reactor Trip System Setpoints Reflect Impact of New Core Limits (OT.iT and OP.iT only) and RAOC 3.1.1.2 Shutdown Margin Mo'fes 3,4, Rcilect impact of .New Boron and 5 Dilution Analysis Limits 3.1.1.3 Moderator Temperature Positive Moderator Coefficient Temeperature Coefficient at Part i

Power 1 3.1.3.4 Rod Drop Time Willincrease to 2.7s Due to Smaller Thimble Guide Tube ID 3.2.1 Axial Flux Difference RAOC (WCAP 10216 PA) with Base Load Option (Similiar to McGuire's Current Tech Spec)

BU Dependent AFD Limits to be Added to Peaking Factor Lirnit Report

3.2.2 Heat Flux Hot Channel New Vantage 5 Fuel Limits with Factor FQ(z)and K(z) Curve inclusion of F Q Surveillance (WCAP 10216 PA)

Third Line Segment of K(z) Curve j to be Eliminated b

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l 3.2.3 RCS Flowrate New Thermal Design Flow that Covers Up to 15% SG Tube ,

Plugging with 2% Flow Margin

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FAH Multiplier to increase from 0.2 to 0.3 3.2.5 DNB Parameters Update with ITDP Uncertainties i

3.9.12 Spent Fuel Storage New Exposure Limits l 3.5.1 Accumulators Contained Water Volume l Requirement increased to reflect l I

, new LOCA Analysis Assumption 5.3 Reactor Core Reload Fuel Maximum Enrichment to Decrease 5.6 Fuel Storage New Burnup/ Enrichment Criteria 6.9.1.11 Peaking Factor Fo Surveillance and BU

Limit Report Dependent AFD Limits i

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SCHEDULE '

item Submittal Date eRack Criticality Report By March 1,1988 eVantage 5 Transition Licensing Submittal , May 16,1988 eCycle 5 Peaking Factor Limit Report Within 30 Days of Cycle 5 Criticality eFSAR Updates Early 1989 I

1988 1989

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1 I I I J F M A M J J A 5 O N D J F M A M J l i I I I I I I I I I I I I I I I I I I I I v//Tw /I */s I I I I I I J L JL J L J ky /" '/5 L J L J L OUTAGE O O vs e e Rack Criticahty Lkenung SD Peaki g FSAR Update Report Submittal Report

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t? . .

MEETING SUF#4ARY DISTRIBUTION

/W NRC PDR '

Local PDR POII-1 R/F

< PAnderson EJordan JPartlow -

-ACRS(10) .

Project Manager John J. Hayes NRC PARTICIPANTS E. Adensam J. Hayes -  ;

R. Jones .

D. Fieno W. Brooks .

E. Branagan l G. Lainas l

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