ML20058P838
| ML20058P838 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/03/1990 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 9008200144 | |
| Download: ML20058P838 (18) | |
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D9cket Nos, 50-369, 50-370 License Nos. NPF-9, NPF-17 Duke Power Company ATTN: Mr. H. D. Tucker, Vice President Nuclear Production Department P. O. Box 1007 Charlotte, NC 28201-1007 Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE
SUMMARY
(NRCINSPECTIONREPORTNOS. 50-369/90-14 AND 50-370/90-14)
This letter refers to the Enforcement Conference held at our request on July 31, 1990.
This meeting concerned activitie.s authorized for your McGuire facility.
The issues discussed at this conference related to the Unit 1 event on June 26, 1990, involving the inoperability of both emergency diesel generators.
A list of attendees, a summary, and a copy of your handouts are enclosed.. We tre continuing our review of these issues to determine the
. appropriate enforcement action.
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 matter, please contact us.
Sincerely,
\\l. % & he
,% u s s Luis A. Reyes, Director Division of Reactor PrNects
Enclosures:
1.
List of Attendees 2.
Enforcement Conference Sunnary 3.
Enforcement Conference Handouts cc w/encls:
T. L. McConnell Station Manager McGuire Nuclear Station 12700 Hagers Ferry Road Cornelius, NC 28078-8985 0
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(Continued)
J. S, Warren Nuclear Production Department Duke Power Company P. O. Box 33189 Charlotte, NC 28242 A. V. Carr, Esq.
Duke Power Company-P. O. Box 1007 Charlotte, NC 28201-1007 J. Michael McGarry. III, Esq.
Bishop, Cook, Purcell and Reynolds 1400 L Street, NW Washington, D. C.
20005 Dayne H. Brown, Director
' Division of Radiation Protection N. C. Department of Environment.
Health & Natural Resources P. O. Box 27687 Raleigh, NC 27611-7687 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, NC 28202 S. S. Kilborn, Area Manager Mid-South Area, ESSD Project Westinghouse Th ctric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, PA 15230 l
Dr. John M. Barry Department of Environmental Health Mecklenburg County 1200 Blythe Boulevard Charlotte, NC 28203 Karen E. Long Assistant Attorney General N. C. Department of Justice P, O. Box 629 Raleigh, NC 27602 State of North Carolina bec w/encis:
(See page 3) 4 5
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3-AUG 0 3 W-i bec w/encis:
D. Hood, NRRa l
M. B. Shymiock, RII A.-R. Herdt, RII_
Document Control Desk s'
NRC Resident' inspector
- U.S. Nuclear Regulatory Commission 12700 Hagers Ferry ~ Rd.
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i ENCLOSURE 1
' LIST OF ATTENDEES 1
U.S. Nuclear Regulatory Commission J. Milhoan Deputy Regional Administrator, Region II (RII) i L. A. Reyes, Director, Division of Reactor Projects, RII l
A. R. Herdt, Branch Chief, Division of Reactor Projects, RII G. R. Jenkins, Director, Enforcement and Investigation Coordination Staff, RII-l D. Hood, Project Manager, Office of Nuclear Reactor Regulation y
K; VanDoorn, Senior Resident Inspector, McGuire i
D. Brady, Office of Enforcement, NRR Duke Power Company H. Tucker, Vice President, Nuclear Production g
T. McConnell, Station Manager, McGuire i
M. Sample, Superintendent, Maintenance i
D. Bumgardner. 0perations Manager D. Murdock, Division Project Managar.
R. Sharp, Compliance Manager B. Gill, Manager, Regulatory' Compliance R. Roberts System Engineer 2
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t ENCLOSURE 2 ENFORCEMENT CONFERENCE
SUMMARY
On July 31, 1990, representatives from Duke Power Company (DPC) met with the
^
NRC in the Region Il office in Atlanta, Georgia to discuss issues concerning the June 26, 1990, inoperability of both Unit 1 diesel generators, operator response to the event, root cause, corrective action and safety significance of the event.
- Following opening remarks by J. Milhoan, Deputy Regional Administrator, DPC gave a presentation (Enclosure 3) on the issues.
T. McConnell, the McGuire Station Manager, presented DPC's presentations.
The presentation covered the event description, root cause, corrective actions, and the safety significance.
-A summary and concluding remarks were made by T. McConnell and H. Tucker.
The NRC closed the meeting by stating that DPC's presentations had served to enhance Region !!'s understanding of the issues and DPC's corrective actions.
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ENCLOSURE 3 l
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ENFORCEMENT CONFERENCE DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNIT 1 DIESEL GENERATOR INOPERABILITY JULY 31,1990
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NRC REGION II OFFICE - ATLANTA
+4++++
AGENDA
+++ve+
- 1. Opening Remarks
- 2. Event Description
- 3. Root Cause
- 4. Corrective Actions
- 5. Safety Significance / Conclusions
- 6. Closing Remarks s
EVENT DESCRIPTION L
l1 I
i October 1988 Maintenance personnel completed painting D/G's 2A and 2B.
May/ June 1990 Maintenance and Opera ^*ons personnel discussed painting Unit 1 D/G's.
June 21,1990 (0800)
Preparations for painting D/G 1A.
L June 22,1990 (0800:
Painted bottom half of D/G 1A. Prepared l
thru D/G 1B for painting.
(1600)
June 23,1990 (0800)-
Painted bottom half of D/G 1B and thru top half of D/G 1A.
(1500)
June 25,1990 (0800)
Painted top half of D/G 1B.
thru (1100) i 9
June 26,1990 (0905)
D/G 1A routine operability Surveillance test performed.
l
(~0910')
Determined D/G 1A start time was slow.
Began investigation.
I (0912)
D/G 1A Shutdown.
I
(~0940)
" Fault Tree" Analysis indicates Valid Failure l
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C (1000)
D/G 1A Declared Inoperable and logged.
Paint noted on both D/G's and investigatingimpact.
(1008)
Second start attempt of D/G 1A. Start time was 10.55 sec, but engine would not fully load.
(1008)
D/G 1A was initially loaded to >2800 kW.
thru Load was gradually reduced to sero, tilien (1047) gradually reloaded to >3200 kW, again unloaded, then reloaded to -3500 kW.
During Load cycling paint did not appear to impede movement of FuelRack.
(1110)
Further investigation determined that paint was probable cause of D/G 1A not loading. Maintenance personnel began removing paint.
Paint noted on fuel pump racks and connections to D/G 1B governor.
Decision reached to remove D/G 1B from service to remove paint, so we could test and verify operability as soon as possible.
(1134)
D/G 1B declared inoperable when control powerbreaker was opened. Technical Specification 3.0.3 and 3.8.1.1.f entered.
Mr
j EVENT DESCRIPTION fcontinued)
(1137)
D/O 1A cleaning of fuel racks completed.
l Operability test started.
i (1300)
PT completed and D/O 1A functional.
(1325)
D/O 1A declared operable.
(1403)
NRC Operations Center was notifled in required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time frame.
(1404)
D/G 1B cleaning completed. Operability test started.
(1600)
D/G 1B declared operable.
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SUMMARY
OF DIESEL GENERATOR OPERABILITI r
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JUNE 26.1990 t
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Problem Declared Operability Operability D/G Identified Inonerable Demonstrated Declared 1
1A
~0910 1000 1300 1325 l
i 1B
~1110 1134 1527 1600
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l ROOT CAUSE ANALYSIS l
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PIESEL GENERATOR PAINTING l
0 Management Deficiency resulting frem l
l inadequate work control.
Inadequate guidance given to painters.
+
1 1
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Did not separate painting of D/G 1A and IB.
i
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No functional verification was required.
l Painting not anticipated to affect 4
+
i operability.
+
Incorrect assumptions made on crew's knowledge.
Independent decision by painters.
+
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ROOT CAUSE ANALYSIS l
l OPERABILITY AND LOGGING CONCERNS i
O Operability Evaluations Background from the Operability Directive
]
+
Operability on D/G 1A declared e
20 minutes late --personnel error 1
Conservatively removed D/G 1B from e
service without testing to remove paint, Correctly logged D/G 1B inoperable e
when control power breaker was opened.
O Same deliberate review, inoperability and operability.
1
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!l PLANNED CORRECTIVE ACTIONS l
1.
Notify appropriate Operational Control Group of paint activities.
i
- 2. A contact person will be designated on work l
l requiring painting of safety-related equipment
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that could be adversely affected by paint.
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- 3. Functional verificsiton required after painting.
4.
No painting on both safety-related trains at the same time, 5.
Changes to the McGuire Maintenance Management Manual.
)
1 6.
Maintenance personnel will be trained.
7.
Event will be covered with all appropriate personnel.
8.
Logging deficiency covered with appropriate shift personnel.
- - - - - - - - - - - - - - ~ * - - - - - - - - - - - ~ " - - - - * * * - * - * - * ' ' ' " ~ ' " '
t SAFETY SIGNIFICANCE l
D/G CONDITIONS l
l 0
D/G 1A Response
+ Initial start -- 11.35 sec vs.11.0 sec requirement.
+ Second start --10.65 sec Loaded to >2800 kW on first attempt.
+ Decreased load to zero and breaker opened.
+ Leaded to >3200kW on second attempt.
+ Decreased load to zero and breaker opened.
+ Loaded to ~3500kW on third attempt.
O D/G IB Response
+ Not tested.
+ Response assumed similar to D/G 1A.
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SAFETY SIGNIFICANC5 DzoloAnligumithmMIR O
FSAR Loads
+
Blackout:
3397kW
+
LOCA (with B/0): 3995kW
+
Many conservative assumptions O
Preoperational ESF Test
+
Observed D/G load:
~3375 kW (ECCS pump flow into Reactor Vessel) q O
Periodic ESF Test j
+
Observed D/G load:
~2700 kW (Major pumps in recirculation flow) i
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SAFETY SIGNIFICANCE CONCLUSIONS 1.
Technically inoperable because Tech Spec requirements not met 2.
D/O's were capable of meeting Design Safety Function i
JUSTIFICATION:
I O
Fuel Racks freed on manual start.
1 O
Rack movement is significantly more pronounced
~
under accident loading.
l 0
Capacity of D/G's sufficient to carry observed Blackout and LOCA Loads.
O Auto start trip - designed to repeat start attempts. Would help free fuel racks.
O Loss of All AC Power EP, manually loads and cross connects Units, i
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ACCIDENT SEQUENCE
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PRECURSOR ASSESSMENT i
O Assessment using NRC Methodology
+
Assumes:
e Loss of all A.C. power, Turbine Driven Auxiliary e
Feedwater Pump available.
e No credit taken for SSF/
l Standby Makeup Pump
+
Estimate of conditional core. damage probability approximately 1E-05 m
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CONCLUSIONS l
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l O
Inadequate work control given for these
- l painting activities.
O Improved work control practices are needed.
1 O
At least one Unit 1 D/G was capable of i
performing its Design Safety Function. Other D/G was in similar condition and could have performed its safety function.
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