ML20236G534
| ML20236G534 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/27/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | James O'Reilly GEORGIA POWER CO. |
| References | |
| NUDOCS 8708040300 | |
| Download: ML20236G534 (26) | |
See also: IR 05000424/1987031
Text
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JUL 2 71987
Docket No. 50-424
)
License No. NPF-68
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1
Georgia Power Company
t, ATTN: Mr. James P. O'Reilly
Senior Vice President-
Nuclear Operations
P. O. Box 4545
Atlanta, GA 30302
Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE SUMMARY - REPORT NO. 50-424/87-45
This letter refers to the Enforcement Conference conducted, at our request, at
the Vogtle site on July 1, 1987. This meeting concerned three potential
violations described in NRC Inspection Report Nos. 50-424/87-31 and
)
50-425/87-37.
These violations represented Technical Specification
1
compliances regarding residual heat removal operability, reactor trip breaker
operability, and diesel generator operability,
i
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Our concerns were expressed to you at the meeting and your positive response to
our concerns was appreciated.
It is our opinion that this meeting was beneficial and has provided for a
better mutual understanding of the inspection findings and enforcement issues.
-
We also found your description of the findings and your corrective actions to
be beneficial in our evaluation of the issues.
In accordance with Section
]
2.790 of NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regula-
i
tions, a copy of this letter and the enclosures will be placed in NRC's Public
Document Room.
Should you have any questions concerning this letter, please contact this
office.
i
Sincerely,
Original Signed by
1
M. L. Ernst/for
i
J. Nelson Grace
Regional Administrator
Enclosures: (See E. Christnot)
1.
Enforcement Conference Summary
2.
Enforcement Conference Technical
Specification Compliance
3.
List of Attendees
(cc w/encis:
See page 2)
8040300 870727
G
ADOCK 05000424
g
. _
_ .
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
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9
Georgia Power Company
2
JUL 2 71987
cc w/encis:
f D. Rice, Vice President, Project
)
Director
LC< W. Hayes, Vogtle Quality
Assurance Manager
i
g Bockhold, Jr. , General Manager,
J
Nuclear Operations
W. Gucwa, Manager, Nuclear Safety
and Licensing
g(Manager
A. Bailey, Project Licensing
)
y W. Churchill, Esq., Shaw,
fittman,PottsandTrowbridge
4
tJ. E. Joiner, Troutman, Sanders,
fockermanandAshmore
,
tp. Kirkland, III, Counsel,
Office of the Consumer's Utility
J
Council
LU,. Feig, Georgians Against
Nuclear Energy
L)if B. Margulies, Esq. , Chairman,
Atomic Safety and Licensing Board
Panel
LDr' O. H. Paris, Administrative Judge
Atomic Safety and Licensing Board
Panel
LG A. Linenberger, Jr. , Administrative Judge
Atomic Safety and Licensing Board
Panel
bec w/encis:
LE'.' Reis, OGC
LM'. Miller, NRR
M.,Sinkule, RII
i
LNRC Resident Inspector
Document Control Desk
State of Georgia
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MSinkule
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07/2V86
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07/jg/.86
07pN86
13
_ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _
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ENCLOSURE 1
4
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ENFORCEMENT CONFERENCE SUMMARY
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On July 1,1987, representatives of Georgia Power Company (GPC) met with the
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,
1
NRC at the NRC's request at the Vogtle site near Waynesboro, Georgia. The main
'
topics of discussion were Technical Specification (TS) compliance regarding the
residual heat removal (RHR) operability, reactor trip breaker (RTB) operabi-
!
lity, and the Trans Delaval Inc. (TDI) diesel generator (DG) operability.
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GPC positions regarding these violations are presented in Enclosure 2.
The
j
security issue addressed in this Enclosure will be discussed in separate
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correspondence.
'
The information presented by GPC basically confirmed the violations regarding
the RHR and RTB compliance.
New information on how GPC interprets the DG
license condition and TS Action Statements was received. Since NRC represen-
l
tatives consider your approach to be a conservative interpretation, the
Violation as indicated as 50-424/87-37-03 " Failure to Follow TS 3.8.1.1 Actions
.
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Regarding the Activities Which Render the Diesel Inoperable" is closed and
Unresolved Item 50-424/87-45-01 " Resolve License Condition and DG Action
Statement Compliance" is open. The purpose for the Unresolved Item will allow
the staff to determine the appropriate course of action.
The current staff
position is that footnotes are part of the Action Statement and since one
i
footnote requires the test to be completed regardless of when the diesel is
returned to service, the licensee remains in the Action Statement while in full
compliance with the LCO. The second footnote then requires that the diesel not
be rendered inoperable when pursuant to the Action Statement.
Your position
being that, while one footnote requires a test only after full LCO compliance
j
is achieved, this is not part of the Action Statement and thus the second
q
footnote does not apply to the diesel.
The NRC, when developing the TDI TS,
however did not consider your approach.
'
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Regarding the RTB, the NRC disagrees with your position that you were in
compliance with Action 13 of TS 3.3.1.
We also note that your interpretat on
provided to the Shift Personnel limits the time-to perform maintenance to less
than two hours until the issue is resolved. Action to resolve the issue rests
soley with your corporate and site organization issuing the correct clarifica-
tion.
Since the event occurred on June 2 and the interim interpretation was
not issued until June 21, the NRC is concerned with your staff's ability to
achieve prompt corrective action to prevent recurrence.
The NRC is presently considering enforcement action of the RHR and RTB issues.
This meeting served to enhance Region II's understanding of the issues.
!
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ENCLOSURE 2
4
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NUCLEAR RE6ULATORY COPfilSSION
1
J
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ENFORCEMENT CONFERENCE
1
1
TECHNICAL SPECIFICATION COMPLIANCE
JULY L 1987
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AGENDA
OPENING REMARKS................................J. P. O'REILLY
1.
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RHR VALVES.....................................T.
V. GREENE, JR.
DIESEL GENERATOR TEST..........................L.
T. GUCWA
REACTOR TRIP BREAKER...........................L.
T. GUCWA
SECURITY ACCESS.....
..........................M. P. CRAVEN
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PROGRAMMATIC ASSESSMENT........................G.
B0CKHOLD, JR.
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CLOSING REMARKS................................J. P. O'REILLY
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RHR VALVE POSITION
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PROPOSED VIOLATION
FAILURE TO DECLARE BOTH RHR TRAINS INOPERABLE AND COMPLY
WITH TECHNICAL SPECIFICATION:3.5.2.
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RHR VALVE POSITION - CONTINUED
0
CHRONOLOGY
APRIL 28, 1987
0
1345
ENGINEER NOTICED AIR PRESSURE ON VALVES
ESTIMATED POSITION 90 - 95% OF FULL OPEN
0
1411
SHIFT SUPERVISOR NOTIFIED, DEFICIENCY CARD
WRITTEN
0
1500
OSOS DECISION - OPERABLE BASED ON
TECH. SPEC. SURVEILLANCE STATUS AND MAIN
CONTROL ROOM INDICATIONS.
OSOS CONTINUED
i
1
REVIEW 0F TECH. SPEC., FSAR, VENDOR PRINTS,
CRANE VALVE MANUAL, AND DISCUSSIONS WITH
ENGINEERING; CONFIRMS "0PERAELE" DECISION.
0
1658
MWO IN WORK PLANNING
APRIL 29, 1987
0
DEFICIENCY CARD TO ENGINEERING
0
2000 MWO COMPLETE
MAY 14, 1987
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DETAIL ENGINEERING REVIEW COMPLETE
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RHR VALVE POSITION - CONTINUED
0
APPLICABLE REFERENCES
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TECHNICAL SPECIFICATIONS 3.5.2
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TECHNICAL SPECIFICATIONS 3.0.3
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RHR VALVE POSITION - CONTINUED
'
0
ENGINEERING REVIEW
0
BASED ON STARTUP TEST DATA
0
TECH. SPEC. FLOW - 3788 GPM
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CALCULATED FLOW
- AT 90%
0.7
TO 2.7% BELOW 3788
- AT 92.5%
> 3788
__
0
CALCULATED POSITION FOR 3788 GPM
- TRAIN A
91%
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- TRAIN B
92.5%
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RHR VALVE POSITION - CONTINUED
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DISCUSSION
0
ALL SURVEILLANCE
SATISFACTORY
0
CONTROL ROOM INDICATIONS NORMAL
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NO POSITION INDICATION ON VALVE
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ENGINEER ESTIMATED POSITION
90 - 95% OPEN
'
- FELT TIP MARKS ON STEM
- POSITIONER CAM
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VALVE THROTTLED FOR PUMP PROTECTION
0
N0 VALVE MAIN 1ENANCE SINCE PREVIOUS SATISFACTORY
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SURVEILLANCE
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- - . - _ _ _ _ . - - _ _ - _ . - - _ _ _ - _ _ - _ _ _ _ . -
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RHR VALVE POSITION - CONTINUED
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CONCLUSIONS
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NON CONSERVATIVE SYSTEM EVALUATION BY ON SHIFT MANAGEMENT
-
SUBSEQUENT INVESTIGATION INCONCLUSIVE
-
FLOW MAY HAVE BEEN BELOW TECH. SPEC.
MARGINAL DEVIATION IF AT ALL
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RHR VALVE POSITION - CONTINUED
IMPROVEMENT ACTIONS
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CALIBRATION FREQUENCY
'
WAS 24 MONTHS
-
NOW 6 MONTHS
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-
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CLARIFICATION OF OPERABILITY DETERMINATION
0
SHIFT PERSONNEL BRIEFED BY PLANT MANAGER
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DIESEL GENERATOR
0
ISSUE
PERFORMANCE OF TEST ON DIESEL GENERATOR PER LICENSE
REQUIREMENTS INSTEAD OF THE APPLICABLE TECHNICAL
SPECIFICATION REQUIREMENTS.
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DIESEL GENERATOR - CONTINUED
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CHRONOLOGY
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JUNE 15, 1987
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BOTH DIESELS OPERABLE
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0321
D/6 IB DECLARED INOPERABLE TO
CHAN6E SEQUENCER TEST CARD
LCO INITIATED PER TECH. SPEC. 3.8.1.1
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0330
0FFSITE SOURCE VERIFICATION COMPLETED
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0331
SEQUENCER MAINTENANCE-COMPLETE
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LC0 CLEARED
BOTH DIESELS OPERABLE
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1650
D/6 1A STARTED FOR SURVEILLANCE
MOISTURE CHECK PER LICENSE
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183'4
D/6 1A STOPPED
-BOTH DIESELS OPERABLE
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DIESEL GENERATOR - CONTINUED
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APPLICABLE REFERENCES
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TECH. SPEC. 3/4.8.1
b,
... PERFORM SURVEILLANCE REQUIREENT
4.8.1.1.2. . 4 AND 4.8.1.1.2. a.5 WITHlW 24 HOURS * #.
NOTE *
THIS TEST IS REQUIRED TO BE COPPLETED REGARDLESS OF WHEN
TE INOPERABLE DIESEL GENERATOR IS RESTORED TO OPERABILITY
NOTE #
TE DIESEL SHALL NOT BE RENDERED INOPERABLE BY ACTIVITIE
PERFORED TO SUPPORT TESTING PURSUANT TO THE ACTION STATE-
ENT (e.g., AN AIR ROLL).
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TECH. SPEC. 3.0.2
...IF TE LIMITING CONDITION FOR OPERATION IS RESTORED
PRIOR TO EXPIRATION OF TE SPECIFIED TIE INTERVALS,
C0fFLETION OF THE ACTION STATEENT IS NOT REQUIRED
.
_ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
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DIESEL GENERATOR - CONTINUED
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DISCUSSION
0
NOTES ARE SEPARATED AND THEREFORE ALLOWS NOTE # TO BE
NOT APPLICABLE WHEN SECOND D/G IS MADE OPERABLE.
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NOTE # NOT APPLICABLE TO TEST DUE TO TECH. SPEC. 3.0.2
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IF INTENDED TO USE BOTH NOTES SIMULTANEOUSLY THERE
WOULD ONLY HAVE BEEN ONE NOTE.
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FIRST APPLICATION OF THIS TECH. SPEC.
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CONCLUSIONS
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BOTH D/G OPERABLE PRIOR TO CONDUCTING SURVEILLANCE
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ACTIONS IN COMPLIANCE WITH TECHNICAL SPECIFICATIONS
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ACTIONS REQUIRED BY LICENSE
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REACTOR TRIP BREAKERS
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ISSUE
SCRAM BREAKER INOPERABLE WITH THE BYPASS SCRAM BREAKER
CLOSED IN EXCESS OF SIX (6) HOURS AS ALLOWED IN TECHNICAL
SPECIFICATIONS.
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REACTOR TRIP BREAKERS - CONTINUED
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CHRON0 LOGY
6/2/87
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1003 HRS
RTB SURVEILLANCE INITIATES
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1100 HRS
ENTERED LC0 1-87-554 ON RTB "B" DUE TO AUTO
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SHUNT TRIP FEATURE
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1142 HRS
REACTOR TRIP. BYPASS BREAKER "B" OPENED
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1214 HRS
RTBB "B" CLOSED TO COMENCE WORK PER
MWO 1-87-06672
0
2048 HRS
RTBB "B" 0PENED
'
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2114 HRS
COMENCED OSP 14701-1 SURVEILLANCE
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2200 HRS
OSP 14701-1 FOR RTB COMPLETE
1
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2201 HRS
CLEARED LCO 1-87-554
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REACTOR TRIP BREAKERS - CONTINUED
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ACTION STATEENT 13 ALLOWS RTB TO BE OPERABLE WITH ONE
DIVERSE TRIP FEATURE IN0PERABLE FOR 48 HOURS.
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ACTION STATEENT 13 ALLOWS THE RTB TO BE BYPASSED WHILE
MAINTENANCE IS BEING PERFORED.
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ACTION STATEENT 10 REQUIRES THE PLANT TO 60 TO HOT STANDBY
WITHIN 6 HOURS IF ONE RTB IS DECLARED IN0PERABLE.
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ACTION STATEENT 10 PERMITS BYPASSING A RTB FOR UP TO TWO '
HOURS TO PERFORM SURVEILLANCE.
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A
R
E
I
S
R
I
N
L
E
U
O
E
E
L
P
Q
C
A
O
E
,
N
N
C
R
R
A
A
I
F
E
H
l
N
O
E
V
l
C
H
L
E
I
C
R
B
W
E
R
E
E
A
O
V
E
B
R
H
R
H
I
M
E
U
T
U
P
S
O
N
O
S
0
R
R
E
1
ELS
U
O
H
O
F
T
N
T
EH
O
S
D
I
H
N
6
R
E
T
T
A
U
D
C
I
H
N
O
I
A
W
C
I
H
V
lll
.._ _ ,
_
'.
.
'
-
.
.
REACTOR TRIP BREAKERS - CONTINUED
l
0
CONCLUSIONS
o
ACTIONS IN COMPLIANCE WITH ACTION STATEMENT 13
'
0
ACTION STATEMENT 10 APPLICABILITY UNCLEAR FOR THIS
SITUATION
0
TRIP RELIABILITY WAS REDUCED WITH THE BYPASS BREAKER
CLOSED WHILE PERFORMING MAINTENANCE
j
i
i
- _ - - - _ _ _ _ _ _ _ _
.
-- -
- - -
. ,._,y
.
..
.
.
.
.
.
.
,
!
REACTOR TRIP BREAKERS - CONTINUED
V0GTLE ACTIONS
0
AN INTERIM TECH. SPEC. INTERPRETATION WAS WRITTEN LIMITING
BYPASS BREAKER CLOSED T0 lWO HOURS.
l
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)
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I
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u
)
_ _ _ - _ _ _ _ _ _ _ _ _
.
l
.
4
ENCLOSURE 3
LIST OF ATTENDEES
NRC, Region II
J. N. Grace, Regional Administrator
A. F. Gibson, Director, Division of Reactor Safety
L. A. Reyes, Director, Division of Reactor Projects (DRP)
G. R. Jenkins, Director, Enforcement and Investigation Coordination Staff
W. E. Cline, Chief, Nuclear Material Safety and Safeguards Branch, Division of
Radiation Safety and Safeguards (DRSS)
M. V. Sinkule, Chief, Section 2C, DRP
J. F. Rogge, Senior Resident Inspector for Operations, Section 2C, DRP
NRC, Headquarters
W. Troskoski, Regulatory Coordinator, DEDRO
Georgia Power Company, (GPC)
J. P. O'Reilly, Senior Vice President - Nuclear Operations
G. Bockhold, General Manager, Vogtle
T. Greene, Plant Manager, Vogtle
E. M. Howard, Manager Nuclear Training, Emergency Preparedness and Security
L. T. Gucwa, Manager Nuclear Safety and Licensing
P. R. Bemis, Manager Plant Support, Vogtle
A. Domby, GPC Legal Representative (Troutman Sanders)
W. E. Burns, Manager Nuclear Licensing
J. E. Swartzwelder, Deputy Manager Operations - Vogtle
D. Smith, Superintendent Nuclear Operations - Vogtle
R. M. Odom, Supervisor Engineering, NSAC
E. M. Danemiller, Technical Assistant to General Manager - Vogtle
Southern Company Services
D. Dutton, Vice President - Nuclear
R. L. George, Manager, NPSD
R. Thomas, Executive Consultant