ML20196G049

Summary of 871202 & 03 Meetings W/Util Re Status of Current & Future Licensing Actions for Plant.List of Attendees,Viewgraphs & Related Info Encl

ML20196G049
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 8803040337
Download: ML20196G049 (25)

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f FEB 2 $ 1985 Docket No. 50-395 DISTRIBUTION:

See attached list

' LICENSEE: South Carolina Electric and Gas Company

o FACILITY: V. C.-' Summer Nuclear Station

SUMMARY

OF MEETING ON; DECEMBER 2 AND 3, 1987-WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY GENERAL ^

On December 2 and 3, 1987, 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 Station in Jenkinsville, S.C.. 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 previded 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.

2.- Incorporation of the new proposed SCE&G organization into the Administrative Section of the Technical Specifications.

3. NRC Regional and Resident Inspector participation at the licensing status meetings.

4. Need for SCE&G to address the'ATWS. Rule.

5. Question on Sumer tendon surveillance.

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

Enclosures:

As stated 8803040337 880229 cc: See next page PDR ADOCK 05000395 P PDR

• SEE PREVIOUS CONCURRENCE

• LA:PD21:DRPR eM:PD21:DRPR D:PD21:DRPR PAnderson JHayes EAdensam 2 / 25/8P 2 /24/88 7/)/ /88

, , 1 Docket No. 50-395 DISTRIBUTION:

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

SUMMARY

OF NEETING ON DECEMBER 2 AND 3, 1987 WITH SOUTH CAROLINA-ELECTRIC AND GAS COMPANY GENERAL On. December 2 and 3, 1987, 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 Station in Jenkinsville, S.C.. 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 Vartage 5 fuel for the next and subsequent reloads.

2. Incorporation of the new proposed SCE&G organization into the Administrative Section of the Technical Specifications.

3. NRC Regional and Resident Inspector participation at the licensing status meetings.

4. Need for SCE&G to address the AT',4S.

5. Question on Sumer tendort surveillance.

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

Enclosures:

As stated cc: See next page

.' e k nI E/ Q 88 l4/27/88 / /88

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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, Jouth Carolina 29218 J. B. Knotts , Jr. , Esq.

Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.

Washington, D. C. 20036 Resident Inspector /Sumer NPS c/o U.S. Nuclear Regulatory Comission Route 1, Box 64 Jenkinsv111e, South Carolina 29065 Regional Administrotor, Region II U.S. Nuclear Regulatory Comission, 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 l

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. ENCLOSURE 1 ATTENDANCE DECEMBER 2-3, 1987 MEETING S.CE&G HEC M. Williams R. Prevatte A. Koon J. Hayes A. Paglia J. Hopkins W. Higgins D. Warner J. Woods L. Cartin 1

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EllCLOSURE 2 AGENDA NRC MEETING WITH SCE&G DECEMBER 2-3, 1987 WEONESDAY. DECEMBER 2. 1987

- Meet with NRC Resident Inspectors 8:30A

- Meet with Plant Manager 9:00A

- Discuss with SCE&G Status of Licensing Actions 9:30A ,

= Discuss Vantage V Core Load Tech Spec Changes 10:00A

- Discuss Future Licensing Actions 10:30A LUNCE 12:00P

• Training for Jack Hayes 1:00P l

Plant Tour and Staff Introductions 3:00P i

THURSDAY. DECEMBER 3. 1987 Meet with 0. Nauman 8:30A l

Meet with NRC Residents 9:00A l

. Nuclear Training Center Tour OPEN I

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Sheet 1 of 6 "

December 1,1.987 I

LICE N51NG ITE MS $TATU5 LIST I V C.5UMMER NUCLE AR 5TATION -

TECHNICAL SPf0FICATION REVl5 TON 5 5UBMITTE D TO NRR FEDERAL NRR TECHNICAL TITLE SUBMITTAL REGISTER NRR APPROVAL SCE 8G REVISION /PROBLE M DATF(5) 155UANCE TECHNkCAL DATE REQUIRED (ISSUE NRR TAC. NO STATUS (Estimated REVIEW (Estimated DATE Date) Date)

, 3/48 " AC $ources* Revises the Technical 5peofication to combine 06-10-85 07-17-85 Remaining TS Partial TS (AMM) testing to reduce thermal transients.(hange 12 06-85 E xp. 08-16-85 Raquest request 59451 18 months surveillance to refueling (hange ,

under review appr aved loading hmits to loading bands, arid other 0644-86 07-30-86 05-30-86 clarifyu.g changes. Exp 07-04 86 NRC comments to be resolved 1st Qtr.

361( "Containment Te(h Spec revised to change the 09-16-86 1145-86 (1241-87)

(RJ8) Structural number / sample of tendons to be tested. August 15 Exp.1245 86 Integrity" deleted speofic tables. and revised the response to minimum required average tendon for(e for NRC 62803 each group. questions 33 "Reactor Trip Technical 5peofication to be revised to 12-08 83 05-06-87 SER being (12-01-87)

Tbl 4 3-1 System optimize reactor trip break er testing Exp 05-05-87 written (HID) Surveillan(e Requirements" 4

53406 I

4623a2 "Reactor 8ldg Revise Tech. 5pec. to require less than 2000 01-20-87 02-26-87 $ER On Hold 4th refueling ru (HJD) Cooling Sys ~ gpm to RBCU's. 02-24 87 Exp 03-28-87 Approved (Awaiting (Giardina) SCE8G r o

64458 release g r

request) :n (a

Shut 2 af 6 '

December 1,1987 LICE N51NG ITE M5 5TATUS Ll5T V C 5UMMER NUCLEAR 5TATION TECHNICAL SPECIFICATION REV1510N5 5UBMITTE D 10 NRR FEDERAL NRR TECHNICAL TITLE SUBMITTAL REGISTER NRR APPROVAL SCE8G

$PEClFICAT!ON REVl510N/ PROBLEM DATE(5) 155UANCE TECHNICAL DATE REQUIRED (ISSUE NRR T AC. NO STATUS (Estimated REVIEW (Estimated DATE Date) Date) 3337 "Fire Detection Evaluate removing all f are Protection f rom 03-31 87 07-29-87 Comments to (03-04 88)

System" Tech.5pec and address m separate document be resolved 3791 "f are Suppression (FSAR) Delete old System

• Igense 3792 "Spray and/or condition Sprinkler Systems" from the 3793 *CO2 System" le(ense and 37.94 "Fire How add GL 86-10 Station" paragraph.

3795 "Yard Fire Hydrants and Hose Stations" 3 7.10 "Fire Rated (HID) Assemblies" 65060 Figures 6 2 Organicsonal Revise Teth. 5 pet to delete organuational 0746-87 (09 09 87) NRC review (03 04-88)

&64 and Iraining (harts and revise tranning requirements on Hold (HID) Changes (RJ8) 65778 Table 4 3-1 "Rea(tor Trip Revise table notation to refle(t that detector 0747-87 (09-09-87) (12-30-87)

(RJ8) System inst. 5urv. plateau (urves are no longer applKable.

Requirements" 65779

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December 1,1987 LICE N51NG IT E M5 5 TAT US LIST V. C. 5UMME R NUCL E AR 5TATION .

TEOiNICAL 5PECIFICATION RE VISIONS TO BE SUBMITTED 4TH OUARTE R 1987 FE DE RAL NRR TECHNICAL TITLE SUBMITTAL REGISTER NRR APPROVAL SCE8G SPECIFICATION REVISION /PRORLE M DATE(5) 155UANCE TECHNICAL DATE REQUIRED NRR TAC NO. STATUS (Estimated REVIEW (Estimated DATE (ISSUE MANAGER)

Date) Date) 30 LCO and incorpos ate standard T5 LCO and Surveillan(e 40 Surveillan(e requirements (GL 8749)

(MDB) Requirements 3/432 ESFAS Revise Table 3.3.5 to(hange notes related to (AMM) Instrumentation Si response times. CVCS valves.

Tbt 3.7-7 Area Temperature Revise temperature for SW pumpAcreen room (AMM) Monitoring

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D:Cember 1,1987 LICENSING ITEMS STATUS LIST V C.5UMMER NUCLEAR 5TATION .

OTHER TECHNICAL REVIEWS TO BE SUBMITTED 987 FEDERAL NRR TECHNICAL TITLE SUBMITTAL REGISTE R NRR APPROVAL SCE&G

$PE OflCATION REV!510N/ PROBLEM DATE(5) ISSUANCE TECHNICAL DATE REQUIRED (iS$UE MANAGE R) NRR TAC NO. STATUS (Estimated REVIEW (E stimated DATE Date) Date) 40 Year O L. Extends O L to 40 4th Qtr. '87 08 02-85 05-07-86 (AMM) years from date of Provide supplementalinformation as Exp 0646-86 issuance requested 59402 (4) 073 7. Item tI D.1 Response to NRC 4th Qtr. '8 7 (AMM) Statf quest ons (letter dated 7 85) pertaining to relief and safety valves These questens ase in (onjurution with NUREG 0737. ttem la D 1.

51606

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December 1,1,987 LICEN5tNG ITEMS $TATU5 UST V. C SUMME R NUCLE AR 5 TAT >ON .

TE CHNICAt. SPECIFICATION RE VI5!ONS TO BE SUBMITTED IST GUARTER 1988 FE DE RAL NRR TECHNICAL T11LE SUBMITTAL REGISTE R NRR APPROVAL SCE 8G

$PECiflCATION REVISION / PROBLEM DATE(5) ISSUANCE TECHNICAL DATE REQUIRED (155UE MANAGER) NRR TAC NO STATUS (Estimated REVIEW (Estimated DATE Date) Date) a 332 "E5F Need to revise Spec. to emplement Will need (CJM) instrumentation" Westanghouse Owners Group optimszatson NRC enput on programs. 3 31 review prior to submittal.

3842 MUV Thermal Delete surveillance requirements for thermal (RJ8) Ove. Sad overlaads that are continously bypassed Add j Protection a. -4 val,es to last and (orre(s typos Bypass Devites 31.1 Shutdown M.-stgin Delete / revise 41 1 1 a and address shutdown (15 8) margin an 3131.

3421

• Safety Valves" Revise T5 to a(comodate testmg of Press and 3422 M5 safety valves m place 3711 (MDB)

(1) 331 "RP5 Need to revise Spec. to amplement To be spist (CJM) inst r umentation" Westinghouse Owner. Group optimization anto two program. submittals 381.1 " A. C. Sources" Evaluate addressing Load Sequencer m a (WRH) separate specifa(atson (Need NRR answer to previous submittal for 3/4 8) 3/445 ~5 team Revise recent Technical 5pecf cation change (TRW) Generator" to corre(t paragraph numbers.

(Administrative Change)

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DeC mber 1,1987 LICE NSING ITE MS STATUS LIST V C.5UMMER NUCLE AR 5TATION OTHE R TECHNICAL REVIEW 5 TO BE SUBMITTED 1988 FEDERAL NRR ESTIMATED IT E M DESCR1P riON ACTUAL REGISTER NRR APPROVAL SCE&G SUBMITTAL (ISSUE __

SUBMITTAL ISSUANCE TECHNICAL DATE REQUIRE D MANAGER) NRR T AC. NO. DATE(5) (Estimated REVIEW " (Estimated DATE Date) Date) j GL 82-33 (1.97) Request for additionalinformation on Reg 1st Qtr. *88 AMM G+ude 197 implementatu>n, t

CR HA8 Report Control Room Habitatulity Report Response 1 st Qtr. '88 AMM AMSAC Prowde plant speofic AMSAC Design 2nd Qtt. '88 MDB GL 83-28 Resolve NRC Questions on Generic letter 2nd Qtr. ~88 j 15 8 83-48 (ATW5) l EOP-GP EOP - Generation Package, resolve NRC 2nd Qtt. ~88

. J58 (omments.

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j VIRGIL C. SUMMER NUCLEAR STATION l CORE RELOAD TRANSITION i

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VANTAGE 5 FUEL E

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l SUMMER PLANT PARAMETERS l Origional Current Future i

! No.of Loops 3 3 3 Fuel Type 17 x 17 STD 17 x 17 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 e Vessel Outlet 618.7 618.7 e Zero Loan 557 557

VANTAGE 5 FEATURES

1. BLANKETS

. 2. INTERGAL FUEL BURNABLE ABSORBER (lFBA) j 3. INTERMEDIATE FLOW MIXER (iFM) GRIDS l 4. RECONSTITUTABE TOP NOZZLE

5. EXTENDED BURNUP WCAP-10444, Reference Core Report - Vantage 5 Fuel Assembly, December 1983.

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LEAD VANTAGE 5 TRANSITION PLANTS 1

i Plants Status l

Callaway 1 NRC SER issued

! Virgil C. Summer Cycle 5 Transition i

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O B J E CTIV E S o Specify Plant Baseline Parameters To Enhance Future Design And Operation Flexibility ,

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o Establish New Licensing Baseline with Vantage 5 Fuel e Core Physics e Core Thermal- Hydraulics e Safety Analyses l e Fuel Storage l

o License The Vantage 5 Baseline For Future Cycles l

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

4 OUTPUTS Item Scope

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! Vantage 5 Transition e Mechanical Design j Licensing Submittal e Nuclear Design o Thermal and Hydraulic Design i e Accident Evaluations

• Technical Specifications l

l Rack Criticality Report e Analyses justifying storage of < 5.0

! w/o 17 x 17 OFA and STD fuel in existing fresh and spent fuel racks with credit for burnup taken e Technical Specifications Cycle 5 Reload Safety Evaluation e WCAP-9272 Scope Per 10CFR50.59 FSAR Updates e Chapters 4,6, and 15 Peaking Factor Limit Report

• Cycle Dependent Power Factors to support Hot Channel Fo Surveillance

NUCLEAR DESIGN Current Cycle 5 Cycle Length 18 mo. 18 mo.

Maximum Enrichment 3.85 w/o 4.2 w/o Fo 2.25 2.45 Fan 1.55 1.62 MTC <0 Slightly Positive at Part Power Control Strategy CAOC RAOC with Baseload Option

CORE THERMAL AND HYDRAULIC DESIGN Current C /cle 5 Key DNBR Parameters

. Power, MWt 2775 2775

. Pressure, psia 2250 2250

. Flow, gpm/ loop 98000 92600

. Tin, F 556. 552.3

. Fs 3 1.55 1.62

. Core Bypass Flow, % 6.4 8.9 DNB Correlations

• W-3 WRB-1 (STD Fuel)

WRB-2 (Vantage 5)

Thermal Design Procedure

• Standard improved Thermal Design Procedure (ITDP)

Consistent with W Topical; "Reference Core Report Vantage 5 Fuel Assembly".

WCAP-10444, December 1983.

ACCIDENT EVALUATIONS .

1. Perform Specific Analyses For e Large Break LOCA (Using BASH *)

e Small Break LOCA (Using NOTRUMP*)

e All Fuel Related Non-LOCA Accidents

2. Justify Continued Applicability of Current e Dose Analyses e Containment P/T Analyses Latest NRC Approved Codes / Methods to be used in LOCA Analyses

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 Procedure and FaH = 1.62 l 2.2.1 Reactor Trip System Set Reflect Impact of New Core  !

(OTATand OPATonly) points Limits and RAOC 3/4.1.1.2 Sutdown Margin - Modes 3,4, Reflect impact of New Boron and5 Dilution Analysis Limits 3/4.1.1.3 Moderator Temperature Positive Moderator Coefficient Temperature Coefficient at Part Power 3.1.3.4 Rod Drop Time Will increase To 2.7s Due to Smaller Thimble Guide Tube ID 3/4.2.1 Axial Flux Difference RAOC(WCAP 10216 PA)with Base Load Option (Similiar to McGuire's Current Tech Spec) 3/4.2.2 Heat Flux Hot Channel New Vantage 5 Fuel Limits with Factor-F Q(z)and K(z) Curve inclusion of Fo Surveillance (WCAP-10216 PA) 3/4.2.3 RCS Flowrate New Thermal Desi Covers Up To 15%gn SG TubeFlow that Plugging l

3/4.2.5 DNB Parameters Update with ITDP Uncertainties

3/4.9.12 Spent Fuel Storage New Exposure Limits l

3.5.1 Accumulators Contained Water Volume

! Requirement increased to reflect l new LOCA Analysis Assumption S.3 Reactor Core Reload Fuel Maximum Enrichment to increase 5.6 Fuel Storage New Burnup/ Enrichment Criteria 6.9.1.11 Peaking Factor Fo Surveillance Commitment Limit Report

SCliEDULE Item Submittal Date

@ Rack Criticality Report February 1,1988

@ Vantage 5 Transition May 16,1988 Licensing Submittal

@ Cycle 5 Peaking Factor Limit >60 Days prior to Cycle 5 Report initial Criticality

@ FSAR Updates Early 1989 t 1988 l 1989 I  :

I I J F M A M J J A 5 O N D M I I I I I l I J F A M J I I I I I I i i i i I I I I I j I I I g j IrgEs/1,;r I I I j i I I I L fdf /y;J g

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@ @ O SSD OUTAG Rack Criticality Licensing Peaking FSAR Report Submittal Report Update

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,u f ENCLOSURE 5

. . jf I' J Docket No. 50-395 CO REQUEST FOR INFORMATION ON VIRGIL SUMER TENDON SURVEILLANCE BY STRUCTURAL AND GEOSCIENCES BRANCH

1. In your calculation of required prestressing forces as given in Filing Code 1.18.2 you use the values provided in FSAR Section 3.8.1.3.1 as the bases, indicate how these values were established, specifically all the values given in item 3 on page 3.8-16 and the factors 1.14, 1.18 and 1.15, and where these factors are used in the calculation. On page 5 of Filing Code 1.18.2 how the force of 10073.8 psf and the factor 1.145 were obtained. Also on page 11 how the number 11,700 psf and the factor 1.1825 were established.

2. It is claimed that the tendon elongation under accident pressure will produce a corresponding increase in tendon force.

In staff's opinion such increase should not be relied on due to the fact that portions of the tendon near the anchorage may be in the non-linear or plastic range and any increase in the elongation may not increase the tendon force to any appreciable amount. This is especially true for curved tendons such as the hoop and dome tendons, i 3. From the informhtion provided in identifier 1.18.6 on non-interaction method and interaction method as well as in Reference 2 on page 12 of the same identifier, the computation of prestress losses and tendon forces is

2-tions of simple sketches the loca Identify in interaction and specific tendon groups. third surveillance - tendons shown in Table 1 of the9 vertical tendons, 50 hoop tendons 18.6.  !

ises (8

s. r. curve) and the 3page 3 of identifier 1 doce tendons tabulated on does not give any page 2 of Enclosure the c3ontainment

'he information provided on of the tendon For each forces in the tendon conditions ff forces is given. retensioning insight into the after well as because no information on lif t-o ing as i ation section or forces at detensionwith technical specif c However, from lif t-of f force tests.

In accordance should be given. should undergo lift-off 5 tendons in s in Surveillance No.1, Pro-d 3 are listed.

4.6.1.6.1, the table fifteen tendonson page as required by 2, only 10

, ll tendons Surveillance No. 2 and 3 tenon lif t-off forces of a vide the information in technical specificat o .

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MEETING

SUMMARY

DISTRIBUTION.

t)gsbet*4e(t\G 50T396~

NRC PDR '

Local PDR '

.PDII-1 R/F

-! Anderson EJordan-JPartlow ACRS (10)

Project Manager John J.- Hayes NRC PARlICIPANTS R. Prevatte J. Hopkins J. Hayes l-