ML20140G020
| ML20140G020 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/28/1997 |
| From: | Skinner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mccoy C SOUTHERN NUCLEAR OPERATING CO. |
| References | |
| NUDOCS 9705060210 | |
| Download: ML20140G020 (42) | |
Text
..
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April 28, 1997 l
l l
Southern Nuclear Operating Company. Inc.
. ATTN: Mr. C. K. McCoy Vice President Vogtle Electric Generating Plant P. O. Box 1295 Birmingham. AL 35201-1295 i
SUBJECT:
MEETING
SUMMARY
- V0GTLE ELECTRIC GENERATING PLANT J
SELF-ASSESSMENT - DOCKET NOS.-50-424 AND 50-425 Gentlemen:
This refers to the meeting conducted at your request at the NRC Region II Office on April 21, 1997 at 10:00 am.
The meeting's purpose was to discuss
)lant performance during the past SALP cycle for your Vogtle facility.
4 Enclosed are a list of attendees and the presentation handouts.
t In accordance with Section 2.790 of the NRC's " Rules of Practice." Part 2.
Title 10 Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this meeting, please contact me at (404) 562-4520.
Sincerely.
I (Original signed by Pierce H. Skinner)
Pierce Skinner. Chief t
Reactor Projects Branch 2 Division of Reactor Projects Docket Nos.:
50-424, 50-425 License Nos.: NPF-68. NPF-81 i
Enclosures:
1.
List of Attendees 2.
Vogtle Performance Graphs l
3.
Vogtle Performance Update cc w/encls:
(See Page 2) t
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f 9705060210 970428 DR ADOCK 050004 4 ll ll I.llll ll lll ll SN5'
SNC 2
cc w/encls:
W. G. Hairston. III President and Chief Executive Officer Southern Nuclear Operating Company. Inc.
P. O. Box 1295 Birmingham. AL 35201 J. D. Woodard Executive Vice President Southern Nuclear Operating Company. Inc.
P. O. Box 1295 Birmingham. AL 35201 J. B. Beasley General Manager. Vogtle Electric Generating Plant Southern Nuclear Operating Company. Inc.
P. O. Box 1600 Waynesboro, GA 30830 J. A. Bailey Manager. Licensing Southern Nuclear Operating Company. Inc.
P. O. Box 1295 Birmingham, AL 35201 Jim Hurt. Director Consumers' Utility Counsel Division Governor's Office of Consumer Affairs 2 H. L. King. Jr. Drive Plaza Level - East: Suite 356 Atlanta. GA 30334-4600 Office of Planning and Budget Room 615B 270 Washington Street. SW Atlanta. GA 30334 Office of the County Commissioner Burke County Commission Waynesboro. GA 30830 Harold Reheis. Director Department of Natural Resources 205 Butler Street. SE Suite 1252 Atlanta. GA 30334 cc w/encls cont'd: '(See Page 3)
SNC 3
cc w/encis:
Continued Thomas Hill, Manager Radioactive Materials Program Department of Natural Resources 4244 International Parkway Suite 114 Atlanta, GA 30354 l
Attorney General Law Department 132 Judicial Building Atlanta, GA 30334 Thomas P. Mozingo Manager of Nuclear Operations Oglethorpe Power Corporation 2100 E. Exchange Place l
Tucker, GA 30085-1349 Charles A. Patrizia, Esq.
Paul. Hastings, Janofsky & Walker 10th Floor l
1299 Pennsylvania Avenue Washington, D. C.
20004-9500 Steven M. Jackson Senior Engineer - Power Supply i
Municipal Electric Authority of Georgia 1470 Riveredge Parkway NW Atlanta. GA 30328-4684 Distribution w/encls:
i P. Skinner, RII R. Carrion, RII W. P. Kleinsorge. RII M. E. Ernstes. RII
)
L. Wheeler NRR PUBLIC l
Distribution w/encls cont'd:
(See Page 4) l I
4 I
_= -. -. - -. -
1
[
SNC 4
i Distribution w/encls:
Continued NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission 8805 River Road Waynesboro, GA 30830 1
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O fvFICE
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SIGNATURE NME NEErnstes:dka PHSkinner j
I DATE 04 / 10 / 97 01 /
/ 97 04 /
/ 97 04 /
/ 97 04 /
/ 97 04 /
/ 97 COPY?
YES (NW rE)
NO YES NO YES NO YES NO YES NO i
UF F 101 AL Rtt,UKU CDPY M,UMtN1 hAMt: A ttiING. M j
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LIST OF ATTENDEES NRC H. Berkow, NRR C. Casto, DRS M. Ernstes. DRP J. Jaudon, Director DRS C. Ogle VEGP Senior Re.sident Inspector L. Reyes, Regional Administrator W. Rogers. Senior Reactor Analyst P. Skinner, DRP, Branch 2 Chief L. Wheeler, NRR Southern Nuclear Ooeratino Comoany. Inc.
B. Beasley, Plant Manager B. Burmiester, Engineering Manager L. Ward, Engineering & Licensing Manager
=
l Vogtle Electric Generating Plant b
S Performance Index 100
. 4*
95
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g
. /J
~
w 90 x
85
/N s
80 75 YearQuarter 941 942 943 944 951 952 953 954 961 962 963 964 971 Unit 1
+ 91.06 92.79 93.69 91.22 92.03 94.25 95.52 95.41 94.96 85.33 90.80 90.70 92.49 Unit 2
+
89.76 93.16 89.98 90.50 87.16 89.57 92.05 93.07 93.26 92.92 88.10 95.10 96.40 Ind. Median 77.00 79.00 79.00 79.00 81.00 82.00 81.00 83.00 84.00 84.00 86.00 85.00 NA
s i
Unit Capability Factor Percent 100 Unit 1 l
- _ _, _ in -
?
~"
i Unit 2 Y
80 i
Industry 60 Unit 1 = 88.8 Median Unit 2 = 91.6 40 Industry = 82.8 Vogtle Goal l
20 Industry Goal
....g
(
0 87-89 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals i
3 Year Average I
i l
Unplanned Capability Loss Factor l
I 12 Unit 1 Unit 1 =5.1
\\
Unit 2 = 4.2 10 Unt2 Industry = 7.2 t
8
~
Industry l
Median 6-i Vogtle 4
Goal l !
_ 4 _. __ g...
Industry 2
Goal
.. g...
0 87-89 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals 3 Year Average l
i
9 Unplanned Automatic Scrams Scrams per 7000 Hours Critical 6
Unit 1 Unit 1 = 0.9 5
Unit 2 = 1.2 Unit 2 i
industry = 0.8 0
4 Industry Median 3
Vogtle 2
Goal t
1
" N - -* --M..
Industry Goal j
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i o
i 87-89 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals 3 Year Average t
G
SSPI-High Pressure Safety Injection Unavailability Factor 0.025 l
Unit 1 Unit 1 =0.004 Unkt2 0.02 Unit 2 = 0.002 0
L Vogtle 0.015 l
Goal 0.01 Industry Goal
..g..
0.005
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IM t
88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals 3 year average I
l
l SSPI-Auxiliary Feedwater System l
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Unavailability Factor l
0.03
}
Unit 1 l
l Unit 1 =0.001 l
l 0.025 Unit 2 = 0.004 Unit 2 1
1 0.02
- - * - ~
Vogtle Goal l
0.015 j
industry 0.01 Goal l
..g...
l 0.005 t
0 f
t 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals 3 Year Average l
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SSPI-Emergency AC Power i
Unavailability Factor 0.04 Plant
=
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. g...
Industry 0.02 Goal
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0.01 i
O 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals 3 Year Average
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I Collective Radiation Exposure l
l Man-rem 350 Unit 1 =148 Unit 1 l
300 Unit 2 = 148 Unit 2 Industry = 147 e
j 250
~
Industry Median 200 Vogtle
{
150 Goal Industry 100 Goal
_..g..
j 50 87-89 88-90 89-91 90-92 91-93 92-94 93-95 94-96 2000 Goals j
Man-rem per unit per year,3 year average l
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Industrial Safety Accident Rate per 200,000 man-hours 3
Station 2.5 Plant = 0.47 Industry = 0.41 Industry Median 2
Vogtie 1.5 Goal 1
Industry x
Goal
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0.5 i
0 l
1990 1991 1992 1993 1994 1995 1996 2000 Goals
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I Thermal Performance t
Unit 1 100 l
Unit 2 Unit 1 = 99.9 Industry 95 Unit 2 = 100.0 i
Median Industry = 99.6 i
i Vogtle 90 i
Goal i
t Industry 85 Goal
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80 1989 1990 1991 1992 1993 1994 1995 1996 2000 Goals I
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i PEER PLANT COMPARISON l
CUMULATIVE CAPACITY FACTOR l
DATA THROUGH DECEMBER 1996 O
100 -
l 81.8 79.7 79.6 79.3 80 -
i
PEER PLANT COMPARISON I
AVERAGE OUTAGE LENGTH i
DATA THROUGH DECEMBER 1996*
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200 150 l
150 l
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100 j
i N N 75 76 D D 79 87 81 83 C... :. ~,Illlllllll 68 70 59 60 62 62 63 f
DATA PROVIDED BY WESTINGHOUSE NUCLEAR SERVICES
Non-Outage Corrective MWO Backlog Not FWC 400 300 g
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Major Problems List
= Control rod guide tube support pin assembly failure.
Steam generator # 4 tube sheet degradation.
= Fuel Reliability Issues.
= Self Assessment / Complacency.
Conservative Decision Making i
l l
= During the 1R6 refueling outage, the decision was l
made not to enter a reduced inventory condition and hence incurred additional critical path outage time.
= In May 1996, a manual reactor trip was initiated in response to inadequate feed flow to Unit 1 SG # 4.
Rapid identification and response reflected positively.
il
= As a result of the loose part in SG # 4, the controls in place prior to and during fueled midloop were noted to be conservative.
1
h Conservative Decision Making
= In October 1996, a manual reactor trip was initiated due to a failed MFRV. The rapid identification and j
response to the event indicated good performance of the operating crew.
i i
i i
In October 1996, an NOUE was declared due to the j
loss of the Unit 2 annunciator function. The i
conservative actions taken in response to this event were considered appropriate.
l l
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= After a Unit 1 trip due to a maintenance technician l
touching a metal tag, actions taken by operations i
were considered conservative.
l
f NRC Identified Strengths
= IR-96-02, Strong operator performance during RCS draindown conducted in preparation for reactor vessel head removal.
= IR-96-02, The ISEG evaluation of the Unit 1 RCS loss j
of inventory was noted to be thorough, well done and j
considered a strength.
= IR-96-02, HP postings observed throughout the plant j
were good and considered a strength.
j i
= IR-96-02, The investigative review of the Unit 1 reactor head stud engagement deficiency was considered a strength.
I NRC Identified Strengths l
t
= IR-96-05, Quick actions to diagnose and initiate manual action to terminate an RCS transient due to a failed open steam dump valve, reflected positively on i
the operating crew.
= IR-96-10, The detailed pre-evolution brief by the performance team for MSRV testing was considered noteworthy.
= IR-96-14, The results of an event review team to i
determine the root cause of failed journal bearing was considered a strength.
j
i Self Assessment Programs Effective Departmental Assessments are being l
=
conducted quarterly. These also serve as a basis for j
strengthening the training program.
i i
= The number of Audit Finding Reports issued by SAER have increased over the last 2 years.
i
= ISEG reviews are effectively used by line management, especially the configuration control assessment and refueling outage risk assessments.
i i
i
Self Assessment Programs
[
= The threshold for reporting Deficiencies has been lowered.
1995-357 1996-899 t
i h
= Use of industry operating experience.
Licensee Event Reports
- 1. Accumulator crosstie.
- 2. P4 Testing.
j i
Non-Cited Violations i
24 4
I
Plant Accomplishments VEGP had an 84.2 % capability factor for 1996 and a j
=
98.3 % capability factor for the first quarter of 1997.
2 refueling outages in 1996 with no significant safety
=
problems.
Completed record 411 day operating cycle for Unit 2 prior to the 2R5 refueling outage. 2R5 outage was 34 days and 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
4 i
Successfully completed mid-cycle Unit 1 j
=
maintenance outage.
t
1 Plant Accomplishments Maintained high standard of materiel condition for the
=
plant with low work order backlog and focus on the age of the backlog.
Effectively implemented improved Technical Specifications for both units.
j 4
FSAR review completed with no significant safety
=
issues identified. Initiated appropriate action for i
discrepancies identified.
Operational Safeguards Response Evaluation
=
concluded that overall, the security force demonstrated an effective contingency response capability.
t Plant Accomplishments l
t l
= All the accredited training programs had l
accreditation renewed. This was accomplished with l
no INPO identified problems.
l
= Enhanced maintenance training using a flow loop simulator.
i i
i Management participation / involvement in training I
programs.
t
+
l l
Training Programs Re-accreditation l
= Nonlicensed Operator
= Reactor Operator
= Senior Reactor Operator j
= Shift Supervisor j
= Instrument and Controls Technician
= Electrical Maintenance
= Mechanical Maintenance j
= Chemistry Technicians
= Radiological Technicians
= Engineering Support Personnel
l Plant Accomplishments j
i i
= Successful Graded Exercise with only one exercise weakness.
t i
= Maintenance Performance Team implementation throughout this SALP period.
i
= Health Physics initiated a centralized remote l
monitoring station.
= EDF exchange program.
Significant Equipment Reliability j
Improvements l
= The refurbishment of the Nuclear Service Cooling Water Pumps.
i
= The changeout of the Reactor Coolant Pumps.
= Partial re-wedge of the Unit 2 Main Generator.
t
= Unit 2 Control rod guide tube support pin assembly l
inspection. Change-out plans scheduled for the 1R7 and 2R6 refueling outages.
l
= Motor Operator Valve modifications and enhancements.
a
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Other Plant Challenges l
i Safety injection motor cooler.
=
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Containment closeout.
=
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Radwaste shipment exceeded limits.
=
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i Engineering & License Initiatives i
Submitted SF rack credit for boron analysis for approval.
= Purchased Maine Yankee boral fuel racks.
= Preparing for 1st SSFA, as stated in 50.54(f) response.
= Analysis of SG #4 tubesheet damage.
= Will provide on-line FSAR, with search capability.
l
= Conversion of IPE model and development of EOOS for risk evaluation.
t l
OPPORTUNITIES
= DEVELOPMENT OF SYSTEM ENGINEERS
= MAINTENANCE RULE SELF ASSESSMENT
/ INSPECTION SYSTEM PERFORMANCE MONITORING l
/ RELIABILITY INITIATIVES l
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HIGHLIGHTS i
BI-WEEKLY SYSTEM ENGINEER REFRESHER TRAINING MINIMAL ENGINEERING BACKLOG
=
AVERAGE PLANT HEAT RATE ~10,000
=
BTU /KWH ALL SSPI AT < 0.5% UN,1VAILABILITY TRANSITION TO ITS
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