ML19332F023
| ML19332F023 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 11/29/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8912130292 | |
| Download: ML19332F023 (35) | |
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NOV 2 91989 s
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t-Docket No. 50-395 License No. NPF-12 South Carolina Electric & Gas Company
- ATTN:- Mr. O. S. Bradham 1
Vice President, Nuclear Operations
! Virgil-C. Summer Nuclear Station P. 0 Box 88 Jenkinsville, SC -29065 Gentlemen: -
SUBJECT:
. MEETING
SUMMARY
- V. C. SUPEER This' refers to.a Management Meeting held in the Region II Office on November 14, 1989.; This meeting was conducted.at your request to discuss your evaluation of -
nuclear operations at the V.C.. Sunener facility.
It is-our opinion that.this meeting was beneficial to better understand past-performance and current issues at your ' nuclear-power facility.
Such open and frank discussions are encouraged.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,
- Title'10,. Code of Federal. Regulations, aJ copy' of - this letter and its enclosures will be placed in the NRC Public Document Room.
'Should. you have any questions. concerning this matter, we will be pleased to -
discuss them.
Sincerely, (Original signed by SDEbneter)
Stewart D. Ebneter Regional' Administrator
Enclosures:
1.
Meeting Summary l?. List of Attendees
- 3.
Presentations Handout cc w/encls:
(See page 2) 8912130292 891129 PDR ADOCK 05000395 P
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NOV 29 m9 South Carolina Electric & Gas
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Company-cc w/encls:
~ J. L. Skolds, General Manager bec w/ enc 1:
Nuclear Plant Operations J. J. Hayes, NRR Summer Nuclear Station Document Control Desk P. 0. Box 88 (Mail Code 300)
Jenkinsville, SC 29065 NRC Resident Inspector U.S.
Nuclear Regulatory Commission A. R. Koon, Jr., Manager Route 1, Box 64 Nuclear Licensing Jenkinsv111e, SC 29065 m
Summer Nuclear Station
- P. O. Box 88 (Mail Code 612)
Jenkinsville, SC 29065
!L J. B. Knotts, Jr.
Bishop, Cook, Purcell &'Reynolds 1400 L Street, NW Washington, D. C.
20005-3502 W'.'A. Williams, Jr.
Technical Assistant Nuclear Operations - Santee Cooper c/o S. C. Electric & Gas Company P. O. Box-764 (Mail Code 153)
Columbia, SC 29218 R. E. Rainear' Executive Vice President South Carolina Public Service Authority P. O. Box 398 Moncks Corner, SC 29461-0398
~
Chairman, Fairfield County Council P. O. Box 293 Winnsboro, SC 29180
~ Attorney General i -
-Box 11549 Columbia, SC 29211
-Heyward G. Shealy, Chief Eareau of Radiological Health South Carolina Department of Health
'and Environmental Control 2600 Bull Street l
Columbia, SC 29201
-State of South Carolina RII RP
'RII: R R F'I A
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ENCLOSURE 1 MEETING
SUMMARY
South Carolina Electric & Gas Company (SCE&G) opened the meeting with an introduction by the Vice President, Nuclear Operations.
Discussion of SCE&G's effort to enhance root cause analysis capability and the use of contractor
~ talents to analyze specific, recent hardware issues was presented.
The General: Manager, Nuclear Plant Operations provided an overview of 1989 performance at V.C. Summer which was less than the Company's goal.
He then discussed major events that lead to the low. plant availability for this year.
Further discussion involved licensee initiatives to improve performance.
The General Manager, Engineering Services discussed licensee plans on current hardware issues, namely Steam Generator integrity and Pressurizer Safety Valve events.
Strategic planning efforts to resolve these hardware items were thoroughly described.
The Vice President concluded the licensee's presentation with a description of other management initiatives and indicators of full corporate support of the operation of the V.C. Summer facility.
The Regional Administrator expressed his appreciation for the licensee's open and candid discussion and encouraged continued efforts for open lines of communications as issues arise.
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ENCLOSURE 2
. LIST OF ATTENDEES j
South Carolina Electric & Gas
- 0. S. Bradham, Vice. President, Nuclear Operations q,
J. L.1Skolds, General Manager, Nuclear Plant Operations.
D. R. Moore, General Manager, Engineering Services
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N Nuclear Regulatory Commission:
S. D.: Ebneter, Regional Administrator, Region II (RII)
J; L. Milhoan,-Deputy Regional Administrator, RII L' A. Reyes, Director, Division of Reactor' Projects', RII~
E.! G.' Adensam, Director, Project Directorate 11-1, Office of Nuclear Reactor Regulation E. W. Merschoff,' Deputy Director, Division of Reactor Safety, RII D. M. Verre111 Chief,. Projects Branch 1, RII 4
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-SOUTH CAROLINA ELECTRIC & GAS COMPANY L
V. C. SUMMER NUCLEAR STATION BRIEFING FOR THE NUCLEAR REGULATORY COMMISSION - REGION 11 November 14,1989 10:30 A.M.
AGENDA MR. O. S. BRADH AM, VICE PRESIDENT, NUCLEAR OPERATIONS e-INTRODUCTION e
ROOT CAUSE ANALYSIS MR. J. L. SKOLDS, GENERAL MANAGER, NUCLEAR PLANT OPERATIONS e
OPERATING HISTORY - 1989 e
SECONDARY PLANT OPERATIONS e
EOP AND SOP INITIATIVES MR. D. R. MOORE, GENERAL MANAGER, ENGINEERING SERVICES e
STEAM GENERATOR ISSUES e
PRESSURIZER SAFETY VALVES MR. O. S. BRADH AM e
PERFORMANCE IMPROVEMENTINITIATIVES e
PLANT STAFFING CHANGES e
SUMMARY
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l MAJOR 1989 EVALUATIONS e
NRC -SALP EVALUATION e
NRC EVALUATION OF THE LICENSED OPERATOR l
REQUALIFICATION TRAINING L
PROGRAM L
e INPO PLANT EVALUATION u
L e-INTERNAL SELF-ASSESSMENT l
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l-1" ROOT CAUSE ANALYSIS EFFORT i
e INPO TRAINING OF KEY PERSONNEL l,
e IN-HOUSE TRAINING - DR. CHlU e
PRESSURIZER SAFETY VALVE ROOT CAUSE - DR. CHlU e
CONDENSER BELLOWS / TUBE FAILURE - DR.JUR e-UTILIZING TRAINED PERSONNEL EVENT INVESTIGATION TEAM i
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'4 1989 PERFORMANCE
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Total Availability Factor 77.6 %
a Capacity Factor 65.0 %
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Forced Outage Rate 22.4 %
L Reactor Trips 4 (2 manual)
R Without Pressurizer Safety
- Valves / Condenser Problems l
Availability Factor 87.7 %
L Capacity Factor 75.2 %
Forced Outage Rate 12.3 %
u Reactor Trips 2
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1989:NRCVIOLATIONS t
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e 4 Violations 1 Levellli 2 LevelIV u
L 1 Level V All but one identified by e
Licensee Nine. additional violations were e
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1 1989 LICENSEE EVENT REPORTS L
18 Total Submitted
-10 Personnel error 4 Design /i'nstallation/ fabrication e
error 4 Random equipment failure e
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1989 CHALLENGES m
Secondary Water Chemistry Pressurizer Safety Valves e
Main Condenser Unqualified Operator e
Offsite Voltage Control
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INITIATIVES
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'Eme'rgency Operating Procedures e
l'<EOP's) r L
Completion expected early 1990 Extensive Human Factors changes Comput.erized Procedures L
L System. Operating Procedures e
Applying lessons learned from EOP's Anticipate reducing errors Operations Standards System Walkdowns Scheduled through March 1990 Will maintain up-to-date through procedural controls
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i, CONDENSER PROBLEMS
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Vibration induced tube failures Structural deficiencies Expansion bellows problems Action Plan to Upgrade i
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tf INITIATIVES l
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L l;W Reliability Centered Maintenance e:
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Chemistry improvements e
b' Security improvements e:
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Drawing Legibility improvements L
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REFUEL 4'(RF4) STEAM GENERATOR j
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TUBE PLUGGING r.
SIG A S/G B SIG C TOTAL
- PLUGGED 117 293.
129 539 BEFORE RF4 (2.5%)
(6.3%)-
-(2.8%)
(3.8%)
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- PLUGGED 180 233 175 588
' DURING REFUEL 4 (3.9%)
(5.0%)
(3.7%)
(4.2%)
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- 0F PLUGGED TUBES i
L RECOVERED DURING 17 19 0
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L RF 4 (F*, MISPLUGS)
L TO'TAL # PLUGGED 280 507 304 1091 (6.0%)
(10.9%)
(6.5%)
(7.8%)
- MEETING F*
CRITERIA'DURING RF 4 97 203 69 369 (2.1%)
(4.3%)
(1.5%)
(2.6%)
- OF RF 4 PLUGGED 95 77 51
- 233
"^ A CAND DATES (2.0%)
(1.6%)
(1.1%)
(1.7%)
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' ** 39.6% (233/588) OF THE TUBES PLUGGED DURING REFUEL 4 (FAILED TO MEET F* CRITERIA) WOULD HAVE BEEN CANDIDATES FOR MEETING THE L* CRITERIA.
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L*/F* ALTERNATIVE PLUGGING CRITERIA M
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BETWEEN TUBE & TUBESHEET.
A GIVEN ROLL CONTACT WITHOUT REGARD TO AND DEFECT ORIENTATION
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STRATEGIC PLANNING u
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STEAM GENERATOR STRATEGIC PLAN INSPECTION OUTAGE RESULTS
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EVALUATE PROJECTS OPTIONS DEGRADATION
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GOALS e
Maximize Life of Generators Maintain Plant Output at Full e
Power Rating u
e Minimize Maintenance j
Activities During Outages a
e Integrate SG Actions into Corporate Plans No Forced Outages Due to SG e
Tube Degradation
STRATEGY Continued Assessment of Defect Rates Consider Future Generator
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Change Achieve Goals By:
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Sleeve Tubes I'
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SLEEVING TECHNOLOGY
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CONSIDERATIONS Ability to Subsequently Plug e
Ability to Sleeve Periphery L
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Efficiency of Installation e
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PLUGGINGiMARGINS l
% PLUGGED
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7(93) 18.2 11.8 8.6 8(94) 22.4 13.7 9.0 t
14(03) 48.9 27.3 14.6 15(05) 52.6 28.9 15.9 l
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486 588 REQUIRING.
21 ACTION (3.5%)
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(38.6%)
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193 233
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. CANDIDATES (39.8%)
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Hi EVALUATE REMEDIAL ACTION COMPLETED. HOT LEG PEENING L
ADOPTED BORIC ACID CHEMISTRY OPERATE AT MINIMUM RCS
. HYDROGEN CONCENTRATION REJECTED ELEVATED LITHIUM 1
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1985 OBJECTIVES u
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PURSUING RELIABILITY 1985 TO 1989 HISTORY l
Investigated Design of Loop Seals 1
e Hot vs Cold e
Investigated Test and Set Methods Full vs Gagged Pop e
e Hot Water e
Hot Nitrogen L
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Hydraulic Device e.
Mechanical Device s
Selected Best method e
SPVD in Cubicle (Set Verification Device) point Continued Pursuit of Facility to Duplicate in Place Setting l
3-1989 CHRONOLOGY o
Began Cycle 5 (SPVD in Cubicle)-
2 Valves Leaking Less than Tech Spec Values 5
e Plant Shut Down for Resin intrusion 3 Valves Leak Tested and Set at W Banning Ca.
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e Plant Restarted - No SPVD in Place e
B & C Leaking C Lifted (Suspected Loss of Loop Seal) e Plant Shut Down - B & C Sent to Banning e
'B' Reworked - Tighter Tolerances e
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'C' Evaluated for Root Cause 1
Plant Restarted - SPVD in Place (Confirm Correlation) o
'A' Began Leaking-e Monitored Daily <400 (@ approx. 390 weeks) e e
Temp Exceeded 400 - Notification Made Temp Quickly Exceeded 450 - Loop Seal Lost o
e Valve Lifted e
Restarted Plant - Current Status Re alaced 'A' with Valve Set to Tighter e
To erances Changed Admin Shutdown Limit to 390 F Based e
on Experience Added Planning Activities @ 350 per NRC e
Request L -
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Redesign for Steam Seat Valves j
e No Loop Seal / No Setpoint Change Safety Analysis forTech Spec e
Change for 3% Tolerance t
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PROFESSIONALISM SELF-ASSESSMENT e
NUCLEAR PLANT EXCELLENCE l
PROGRAM (NUCLEX) i I
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PROFESSIONALISM SELF-ASSESSMENT e
EMPLOYEE CONCERNS e
"DOWN-SIZING" NEIGHBORING UTILITIES e
"MORE-FOR-LESS" PERCEPTION e
MANAGING CHANGE NEEDS 1
IMPROVEMENT l
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COMMITMENT TO BE A TOP PERFORMER e
MANPOWER e
BUDGET
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NUCLEAR PLANT EXCELLENCE (NUCLEX) t e
e IDENTIFY STRENGTHS e
IDENTIFY AREAS FOR ENHANCEMENT c
e DEVELOP AND IMPLEMENT 1
STRATEGIES FOR EXCELLENCE k
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STRATEGIES AND ACTION PLANS e
MANAGEMENT EFFECTIVENESS P
o STABILIZING PLANT PERFORMANCE 1
o OUTAGE PERFORMANCE ENHANCEMENT i
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LONG-RANGE PLANNING o
HUMAN RESOURCE IMPROVEMENT b
o PROGRAM EVALUATION / ENHANCEMENT e
NUCLEAR DIVISION EXTERNAL RELATIONS I
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HUMAN RESOURCES-1989 Authorized Staff-674 1990 Authorized Staff-777 Additions:
e Operations 7
o Chemistry & Health Physics 7
e Maintenance 2
- Training 16 l
e Engineering 44 l
e Nuclear Safety 15 o
e Administration & Support 12 103
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SUMMARY
i ACTION PLANS FULLY SUPPORTED e
BY CORPORATE e
MANAGING PERCEPTIONS KEY TO SUCCESS l
4 1990 INITIATIVE TO IMPROVE OUR e
COMMUNICATIONS WITH NRC 1
MAJOR FOCUS IN THE 90'S IS TO e
IMPROVE OUR ABILITY TO MANAGE i
CHANGE.
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