ML20235W274
| ML20235W274 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/09/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8710160103 | |
| Download: ML20235W274 (17) | |
Text
__
October 9, 1987 Docket No. 50-369 License No. NPF-9 Duke Power Company I
ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE
SUMMARY
(NRC INSPECTION REPORT N05. 50-369/87-26 and 50-370/87-26)
This letter refers to the Enforcement Conference held at our request on September 15, 1987, concerning activities authorized for your McGuire facility.
The issues discussed at this conference related to the inoperability of the Unit 1, Train A, Emergency Diesel Generator (D/G 1A) which occurred between July 26 and July 30, 1987. A summary, a list of attendees, and a copy of your handout are enclosed.
It is our opinion that this meeting was beneficial and has provided a better understanding of the inspection findings, the enforcement issues, and the status of your corrective actions.
We are continuing our review of these issues to detennine the appropriate enforcement action.
In accordance with Section 2.790 of the ARC'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, (Original signed by J. N. Grace)
J. Nelson Grace Regional Administrator
Enclosures:
1.
Enforcement Conference Summary 2.
List of Attendees 3.
Handout cc w/encls: (See Page 2) l 8710160103 871009 I
PDR ADOCK 05000369 G
l PDR l
t \\
\\
ZEol
Duke Power Company 2
October 9, 1987 cc w/encls:
~
T. L. McConnell, Station Manager Senior Resident Inspector - Catawba bec w/encls:
J. Lieberman, DOE G. R. Jenkins, EICS D. Hood, NRR I
NRC Resident Inspector Document Control Desk State of North Carolina J
R1 R
PP R
RII
[#MLewis:ser LLawyer
[tTJ0'Connor
/HShymlock CJulian t
10/,t/87 10/ v/87 10/4 /87 10/ o /87 10/ 2./87 I
Ril R
Q AGibson T eebles LReyes Jer; ins MErnst dNGrace i
10/ /87 10/f/87 10/u/87 10/g/87 10/ /87 10/y/87 l
1 l
ENCLOSURE 1 ENFORCEMENT CONFERENCE
SUMMARY
On September 15, 1987, representatives of the Duke Power Company (DPC) met with the NRC to discuss the McGuire Unit 1. Train A, Emergency Diesel Generator (DG 1A) inoperability issue.
The meeting was requested by the NRC and was held in the NRC Regional Office located in Atlanta, Georgia.
DPC provided a presentation, Enclosure 3, describing the sequence.of events, root causes, corrective actions, and safety consequences of the D/G 1A inopera-bility that occurred between July 26 and July 30, 1987. The presentation also provided additional information regarding the operability of the turbine driven auxiliary feedwater pump and the nuclear service water system valve 1RN-1628.
This and other information presented in the Enforcement Conference will be considered 'in our. review of determining the appropriate enforcement action pertaining to the D/G 1A issue.
l l
)
(
L_-__
l f
1 ENCLOSURE 2 s
1 i
ENFORCEMENT CONFERENCE LIST OF ATTENDEES LICENSEE: Duke Power Company DATE: September 15, 1987 FACILITY: McGuire Nuclear Plant IR NO:
50-369, 370/87-26 NAME
' POSITION / TITLE ORGANIZATION J. Grace Regional' Administrator NRC, Region II L. Reyes Director, DRP NRC, Region II T. Peebles Acting Branch Chief, DRP NRC, Region II W. Orders Senior Resident Inspector, NRC, Region II McGuire M. Shymlock Section Chief, OPS NRC, Region II B. Bonser Project Engineer, DRP NRC, Region II T. O'Connor Reactor Engineer, DRS NRC, Region II M. Lewis Reactor Engineer, DRS NRC, Region II L. Lawyer Reactor Engineer, DRS NRC, Region II B. Uryc Enforcement Coordinator, EICS NRC, Region II G. Swindlehurst Sup. Design Engineer Duke Power E. McCraw Compliance Engineer, McGuire Duke Power H. Pastis Acting Project Manager, McGuire NRC/NRR A. Herdt Branch Chief, DRS
,NRC, Region II G. Jenkins Director, EICS NRC, Region II A. Gibson Director, DRS NRC, Region II B. Travis Superintendent of Operations, Duke Power McGuire T. McConnell Station Manager, McGuire Duke Power H. Tucker Vice President, Nuclear Production Duke Power N. Rutherford System Engineer, Licensing Duke Power
\\
--- = _ - _ - - _ - _ - -..
a 4 4'lf
?
.+;
ENCLOSURE'3-~
6
.. r f.
~ DUKE' POWER' bOMPAflY ' HANDOUT
).
g
,s l-McGUlRE l-j:
ENFORCEMENT CONFERENCE l.
SEPTEMBER'.15, 1987 L
e h
SEQUENCE OF EVENTS-T.-L.
McCONNELL ROOT CAUSE/ CORRECTIVE' ACTIONS R.
B. TRAVIS SAFETY SIGNIFICANCE T.
L. McCONNELL
\\
L-..__.._-_.
f I
- a. :
r DIESEL GENERATOR 1A l*
INOPERABLE DUE TO CONTROL i
l POWER BREAKER OPEN SEQUENCE OF EVENTS g
'DATE TIME EVENT q
i fA NEW COMPUTER PROGRAM WAS IMPLEMENTED TO 6/15/87 AUTOMATE THE ISSUE OF RED TAGS (PERSONNEL SAFETY TAGS) AND THE REMOVAL AND RESTORATION PROCEDURE.
7/24/87 A POLICY CHANGE WAS IMPLEMENTED THAT REQUIRED THE REMOVAL OF CONTROL POWER FOR ALL COMPO-NENTS THAT ARE COOLED BY THE NUCLEAR. SERVICE WATER (RN) SYSTEM WHENEVER THE RN SYSTEM IS REMOVED FROM SERVICE.
THIS POLICY CHANGE DID NOT REQUIRE THE USE OF WHITE TAGS (EQUIPMENT PROTECTION TAGS).
7/26/87 1800 THE CONTROL POWER CIRCulT FOR DIESEL GENERATOR (D/G) 1A WAS OPENED BY OPERATIONS PERSONNEL AS AN EQUIPMENT PROTECTION MEASURE PRIOR TO A PERIODIC MAINTENANCE EVOLUTION.
7/27/87 0500 OPERATIONS PERSONNEL ERRONEOUSLY RETURNED D/G 1A TO AN OPERABLE STATUS WITH THE CONTROL POWER CIRCUlT BREAKER STILL OPEN.
1430 B AUXILIARY FEEDWATER SYSTEM (CA) PUMP SUPPLY FROM TRAIN B RN VALVE 1CA-188 FAILED A PERIODIC STROKE TIMING TEST.
7/29/87 1415 VALVE 1CA-188 REPAIR AND RETEST WAS SUCCESS-FULLY COMPLETED, AND OPERATIONS PERSONNEL DECLARED THE VALVE OPERABLE.
.i
DATE,
TIME.
EVENT 7/29'/87 A CONTROL ROOM OPERATOR INITIATED A WORK
- - =
REQUEST TO REPAIR THE D/G 1A START /STOP SWITCH ON THE CONTROL BOARD.
7/30/87 0530
- OPERATIONS' PERSONNEL DISCOVERED THE CONTROL POWER. CIRCUIT BREAKER-lN THE OPEN POSITION y
WHEN THEY WENT TO OPEN IT FOR A PERIODIC MAINTENANCE EVOLUTION.
0530-1034 INVESTIGATED REASONS (S) FOR THE CONTROL POWER BREAKER BEING OPEN.
1034 OPERATIONS PERSONNEL' CLOSED THE CONTROL POWER CIRCUlT BREAKER AND BEGAN AN OPERABILITY TEST ON DIESEL GENERATOR.1A.
1230 THE OPERABILITY TEST WAS SUCCESSFULLY-COMPLETED.
1655 THE' CONTROL POWER CIRCUlT BREAKER WAS OPENED AGAIN FOR ROUTINE PERIODIC MAINTENANCE.
7/31/87 0645 THE CONTROL POWER CIRCUlT BREAKER WAS CLOSED, AND DIESEL GENERATOR 1A WAS DECLARED OPERABLE.
DUE TO THE D/G BEING UNKNOWINGLY INOPERABLE FROM JULY 26 THROUGH JULY 30, McGUIRE TECHNICAL SPECIFICATIONS (T.S.) WERE VIOLATED:
T.S.-3.8.1 WAS VIOLATED WHEN THE OFFSITE POWER SOURCES WERE NOT VERIFIED AND WHEN THE L.C.O. ACTION STATEMENT EXPIRED.
T. S. -3. 7.1. 2 WAS V I OLATED WHEN THE L. C.O.
ACTION STATEMENT EXPIRED DUE TO THE B TRAIN CA PUMP BEING INOPERABLE.
l
g-i' ROOT CAUSE i-PRIMARY IMPROPER' INDEPENDENT 1 VERIFICATION OF COMPONENT DID VERIFY D/G 1A EMERGENCY BREAKER CONTROL POWER FUSES, SHOULD HAVE VERIFIED D/G 1A CONTROL POWER BREAKER.
REASONS A)
VERY SIMILAR NOMENCLATURE ON D/G BREAKER AND D/G CONTROL POWER BREAKER COUPLED WITH MISLEADING NOMENCLATURE ON THE REMOVAL AND RESTORATION (RSR)
PROCEDURE.
B)
MISLEADING EQUIPMENT POSITIONS ON RSR PROCEDURE
- LISTED AS."lNSTALLED" SHOULD HAVE BEEN " CLOSED" C)
IMPROPER WORK PRACTICE BY NUCLEAR EQUIPMENT OPERATORS RESTORING.D/G TO OPERABLE
F
[-
i ROOT CAUSE.
SECONDARY CONTROL BOARD REVIEWS ~WERE NOT THOROUGH ENOUGH A)
"OFF" LIGHT ON D/G 1A CONTROL ROOM START /STOP SWITCH WAS EXTINGUISHED J
B) 1.47 BYPASS PANEL LIGHT FOR D/G 1A INOP WAS
-ILLUMINATED REASONS A)
. ANNUNCIATOR LIGHT FOR D/G 1A CONTROL POWER TROUBLE DOES NOT ILLUMINATE WHEN THE CONTROL POWER BREAKER IS OPEN.
B)
THE 1.47 BYPASS PANEL CHECK IS NOT ON THE NEW COMPUTER "RSR" SHEETS.
C)
ALL OTHER MAJOR ESF COMPONENTS CONTROL POWER IS LISTED ON-RO AND NEO TURNOVER SHEETS.
D/G CONTROL POWER WAS NOT.
D)
THE 1.47 BYPASS PANEL HAS NOT RECEIVED THE EMPHASIS FOR OUTSTANDING WORK REQUESTS THAT OTHER CONTROL ROOM INDICATION HAVE, SUCH AS CONTROL ROOM ANNUNCIATORS, METERS OR CONTROL SWITCHES.
E 1 -,.
l PRIMARY CAUSE (IMPROPER INDEPENDENT VERIFICATION)
CORRECTIVE ACTIONS
'A)
TRAINING - A " CASE STUDY" OF THIS EVENT IN REQUAL FOR ALL LICENSED AND NON-LICENSED OPERATORS WILL BE COMPLETED BY 12-15-87.
B)
NEW TAGS WILL BE PLACED AT ALL D/G 4160V BREAKERS STATING PULLING FUSES WILL NOT PREVENT A D/G START.
COMPLETED BY 10-01-87.
C)
THE NUCLEAR EQUIPMENT OPERATORS WERE DISCIPLINED FOR THElR PERFORMANCE.
THE SUPERVISOR WAS COUNSELLED -
COMPLETE.
D)
THE TAGGING POLICY DEVELOPED AT THE. SHIFT SUPERVISORS MEETING WAS CHANGED TO DELETE PULLING FUSES FOR RN PUMP WORK AND TO REQUIRE WHITE TAGGING THE D/G CONTROL POWER BREAKER - COMPLETE.
E)-
INCREASED EMPHASIS IS BEING PLACED ON ALL CONTROL BOARD DEFICIENCIES INCLUDING THE 1.47 BYPASS PANEL.
THESE DEFICIENCIES ARE TRENDED DAILY IN THE MANAGERS PLANT STATUS MEETING - COMPLETE.
a i
1
k j
r
. SECONDARY CAUSE - (CONTROL BOARD REVIEWS)l I
CORRECTIVE ACTIONS A)
A STATION PROBLEM REPORT WAS APPROVED TO CHANGE THE CONTROL' BOARD ANNUNCIATOR FOR "D/G CONTROL POWER TROUBLE" TO ALARM WHEN THE CONTROL POWER BREAKER IS-OPEN.
B)
REVISE THE COMPUTERIZED RSR FORM TO BE MNS SPECIFIC AND INCLUDE THE 1.47 BYPASS PANEL SIMILAR TO MANUAL FORM.
THE FORM HAS BEEN REDESIGNED AND'WILL BE ORDERED BY 10-01-87.
C)
BOTH RO AND NEO TURNOVER CHECK SHEETS HAVE BEEN REVISED i
TO INCLUDE CHECKING D/G CONTROL POWER.
D)
MORE THOROUGH-CONTROL BOARD WALK DOWNS ARE BEING EMPHASIZED TO CONTROL ROOM OPERATORS.
4
7
- i.;
p,
',i',
i{l T
'D/G 1A a
- ^
D/G 1A Emerg. Bkr.
+
4160V Control Power Fuses
)
ww mm-
)
3
,600V-g) i J
EHXE' l
~~~
j) 600V
)
)
EDCA ww
.l
)
mm to 600 vac I
AU11LIAnf Pdsa'P$st
~
- socA
.,oano
)
.__n.
1 i
}
1EDCA 125 VDC D/G 1A
')
)
Control Power Bkr.
1 I
y y
ottsat causaATOR FUEL O!L L
CONft0L PANEL 300 STER PUMP L'
t' t
t l
~
t W
)
R
)
e A
l
(
(
1 2
'S I 2
'A IAA 5 R I
A A
A A
A A '
1 I
5 I 8
I g
g '
1 1
1 I
I B
1 I
1 I
g g
N,p, gg N'D P
A P
P t F P
e M 1
fW P
E F y
P H
D W
M M
M M
U l
R l
U t
s N
p U
t C
A C
E U
t t
g g
U It U
t t
p P
P P
P P
P P
X.
X X. G P P P
P P
C C
l L
l
/
I V
A e
F /
E E
E C C S
B I
Y g
p /
UC D
D K K N H N
N g
g A s
EK M
N M
C t
K A I
1 I
~
~ - '-
, ~ --
~
^
^
O-y :
~
~,-
~ -
)v A
0 S
T 6
TE E
1 I
I 4
~
(
~
1~
g ge I g g l
8 I t
a
~
's l 3 I g g3 g I I P
P f
F M
M r
I P
e U
UFu N
l e
E iM P
P P
e PP h
B P
e t
t t
t B
l Cs P
Cal TP TCA PrRt RPN t
t Pt s
Pe 9
PE t
e Et E
I t
Ct T
t 3P NS RP t
RPS SRR -
)
e 0R OI D rLL At rrI L n
erLL0D PP OF I
M PE a e
e YL R s t e VL C
VLB Mf B R
tB D
9 LE E
t I LE R
Ut NT t t LE D 0 P P U
D PP WDT PP DI H t t N
R00 -
i P P i
T T IB H iA t
II RI I A TX L I aI r FP s
CCA0ET0 D
CC Mr n
t A AAAP CAAL S 5 a5tS QALLS CCCCCCAIT X. L I 2 NR O J I XI BEsR NRl H C 3 A F A X.
I P N0CD X I
t LUTIRL I
l DD B 0A
- 2 S s I S I I SI I I I I 1 l 1 II ES1 I I I I I I I I SI I I i I I I 51 I I
^
7 7b O -
- L
~
' i '.
J * -
)
)
)
V v
V IC~
_0 A-0 0
d 0
D 0
0 T
9 T
i 9
9 6
I t
M 6
(
(
K U
R SD XR T
H O
EE EA E
T W
f C DE R
D P A NL I
R CP A M D
O E
T R E
F IL EL F
M I
T B
N S
D F
E GR E
E D
N OE EMR E E O
T S
O LT RRA T
V Y
P R
FAE A MA N
I I
E t
S S
C P L D T R E
C R
IM E
R T
E R
O N
M U
S E
D EM GR D V D
D IV I
T RR Y
E E
C E C
R f!
OA R MB
/
E E
FA LE O
A G O
T L A P
P RL A
A P P R
U M
C C D
P I
S
- N S E h O D
GE GR R U P
OR OA T
LE LE L
ST S C T N T
E Q O ES N S D E
I V
K P
L D C
O M W8 C A
E C
H A
D R
N E
S R
I V
C D RE R
B y
O B
T Y
E U
E P
E( S:
M D
U Q 8 C
R D
G N O R N E
E)
D D
A OP R N T
)
)
R E
R R O
DR T
1 &
T R(
U O
SN R
O R(
(
G G
T T A
AR D
)
S T
U U T
E R
G & O O O G
G G A
(
P R
T A A T T Q O E
N S
G
)
R A
T R
E
(
T D
I E
H G
W GA T
T N
E M
P tU Q
G E
A T
D 4
E R) 8 R
2 R(
Rt D
8 E
8 R
1 O G N
5 G
R O
3 T
A O
N F L LS I
S T
S M
T T
N A S
AK A
E K
VR R
R MM O V E
R G O O
T S O K
OA O A A N F
PE R U T
M SM T
A OS AM O Q S
OY E E E
Q j
+
u i
ay OP/0/A/6100/09 3.3'
~ ~ '
1.
. a.
Page 1 of 2
,a
%M RESTORATION OF STATION EQUIPMENT
\\
- 1.' O Initial Conditions
' 1.1; Equipment is ready to be returned to service.
,g
- 2.0 Procedure L:
'2.1 Record the following.if using procedure (or M/A).
l Procedure Number and Title I
Enclosure Number and'Name 2.2 Fill out the' Restoration Checklistr Ensure any components covered by a Removal Addition Sheet are identified by placing the applicable letter next'totthem in the left hand column.
L 2.2.1 'If checklist has previously been used for tags that'have been lifted and rehung for testing, then fill out a new-checklist (keep old checklist in R&R).
2.2.2 Use the Control Copy'of the appropriate procedure to determine the Restored position for any component.
2.3 Review the Removal Checklist (Encl. 4.2) and. Removal Addition Sheets (Encl. 4.4, if used). Ensure that the proper restoration sequence is 1
identified to include filling and venting, if required.
-1 2.4 The restoration sequence is verified correct by the Originator, Reviewer and Approver signing EACH Restor.stion Checklist Sheet.
(Init). 2.5' Any' drained piping and/or-component verified filled and vented (or N/A).
(SR0/RO)2.6 Restoration Checklist is complete.
(Init) 2.7' R&R Cross-Reference Sheets removed-(White Copy attached to R&R).
2.8 R&R cleared from RO Logbook (s) (N/A non-affected unit).
l (RO)
UNIT 1 (RO)
UNIT 2 (Init) 2.9 R&R cleared from R&R Index.
(Init) 2.10 Applicable 1.47 Bypass Panel lights out or actuate manually (or N/A).
I (RO) 2.11 Applicable Control Board Stickers removed (or N/A).
i (SRO) 2.12 Tech Spec Action Log (s) updated if applicable (or N/A).
i (SRO) 2.13 R&R completion approved. DATE 2.14 Route completed R&R package to Duty Engineer.
l
=_-
\\
ET o
9~
VO tl 03 IN
/.-
s np 042 l
ee 0
a 4
cr r
i. ~
e 1 ef 6 r o e
t rE
/u s
i eT ps A s2 i
noO
/o-w I DN r
0l e r
os
/cg e
P na h
ss OEP t
nu rf o
u
)
d o3 t
e
.N t
.d/E ew qsT d
V. e e O o
uP n
IRYN l
(
cl s
n se i
( t ln d
u eC d
dn l
e eo 2
t t
ri t
s ot E
ok i
ti T
r l
ss O
h eo N
t e
RP c
T n
dt S
e e
I u
si L
q oL K
e l
C s
c EH n
C i
) i
.tsd Nf e
Oo t
di e I
e elk lk c T
l A
p l ca R -
m uer Ot o
ph T e C
cr S e f
Eh i. v RS E
r dld c T
o eve O
d N
d uyt e ep lbt re c
ot nd r tS 1
i eh s
rt el E
ei Ra T
b ud r
O q
)
t o N
t ek O
nt src
)
R es u
n
/
)
ne mfl i
i R
R p
s.
g O
O oR S
S S
m -
e "d s
(
(
(
o C
uesq f t a
rec es wkd oce Pakl b
l" o
re td y
nun ol e B
Ccpne y
y d
B B
n ri e
t d
d e(dt a
e e
k n
w-v ank i
e o
eec r po g
i r
i v
p e
BOl r
e p
l n
)
O R
A b o s
ait(
1 2 ct er iiee ldht EE pd S t TT pA e
OO
'A L
NN
,.. c SAFETY SIGNIFICANCE VERY LOW SAFETY' SIGNIFICANCE BECAUSE:
DIESEL GENERATOR EASILY. RECOVERABLE
. LOSS OF AC-POWER PROCEDURE PLACES HIGH PRIORITY ON ASSURING BOTH DIESELS ARE IN OPERATION.
l, OTHER DIESCL GENERATOR WAS AVAILABLE DURING THIS TIME PERIOD RN TO CA SUCTION VALVE WAS O'PERABLE WITH AN ACTUATION TIME OF 14.5 SECONDS EVEN THOUGH iT EXCEEDED THE T.S. TIME OF 13 SECONDS.
THE B CA PUMP WOULD NOT HAVE LOST SUCTION WITH THE ACTUATION TIME OF 14.5 SECONDS.
RN TO CA SUCTION IS-ONLY REQUIRED IN THE EVENT THAT AN EARTHQUAKE WITH A MAGNITUDE OF APPROXIMATELY THREE-TIMES SAFE SHUTDOWN EARTHQUAKE (S.S.E.) OCCURS WITH THE MOST y
LIMITING COMPONENTS BEING THE TANKS.
RN TO CA SUCTION IS FOURTH SOURCE 1.
UPPER SURGE TANKS 2.
CA CONDENSATE STORAGE TANK 3.
HOTWELL 4.
RN l
4 VERY LOW CORE DAMAGE POSSIBILITY AND PUBLIC HEALTH RISK AS CONFIRMED BY THE DUKE P.R.A.
MODELS.
l l
1 J