ML20056C165
| ML20056C165 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/02/1993 |
| From: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9303300170 | |
| Download: ML20056C165 (34) | |
Text
gyn a
~
- ;g li g[ ff
- '
t i@R 2 1993 I
iDocket Nos. 50-338, 50-339 Iicense Nos. NPF-4, NPF-7 l
. Virginia Electric and Power Company ATTN: Mr. W. L. Stewart Senior.Vice President - Nuclear 5000 Dominion Boulevard l
Glen Allen, VA i.3060 I
[
Gentlenien:
SUBJECT:
-MEETING
SUMMARY
- NORTH ANNA UNITS 1 AND 2 This letter refers to the technical meeting conducted at your request:at the NRC-Region II office in Atlanta.on February 25, 1993. The purpose of the meetina was to allow the licensee to' make a Self-Assessment follow-up presen-
+
tation. The presentation summary is enclosed.
It is our opinion that th'is meeting was beneficial and provided a better understanding of the licensee's self-assessment program in the areas of 1
Technical Specification Review Program and Quality Assurance Performance Assessment.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, j
Title 10 Code of Federal Regulations, a ccpy of this letter and its enclosures will be placed in the NRC Public Document Room.
l Should you have any questiens concerning this letter, please let us know.
l Sincerely, Original signed by Ellis W.. Merschoff i
Ellis W. Merschoff, Director Division of Reactor Projects
Enclosures:
1.
List of Attendees 2.
Presentation Summary-cc w/encls:
M. L. Bowling,. Jr., Manager Nuclear Licensing l
Virginia ~ Electric & Power Lompany' I
5000 Dominion Boulevard
-Glen Allen, VA 23060.
cc w/encis' cont'd:
(See page 2);
4' l
- ,C f
(
+
9303300170.930302
~.
PDR ADOCK 05000359 i
- 7. jy:
p ppk..
13
~.
i O
f Virginia' Electric & Power 2
PAR 2 1993 Company f
cc w/encls cont'd:
G. E. Kane, Station Manager NRC Resident Inspector Narth Anna Power Station U.S. Nuclear Regulatory Commission i
P. D. Box 402 Route 1, Box 166 i
Mineral, VA 23117 Surry, VA 23883 l
Executive Vice President Old Dominion Electric Cooperative 4201 Dominion Boulevard Glen Allen, VA 23060 Dr. W. T. tough Virginia Corporation Commission P. D. Box 1197 Richmond, VA 23209 William C. Porter, Jr.
County Administrator P. O. Box 160 Louisa, VA 23093 i
Michael W. Maupin, Esq.
Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, VA 23219 Attorney General 101 North 8th Street Richmond, VA 23219 Robert B. Strobe, M.D., M.P.H.
State Health Commissioner
~
P. C. Box 2448 Richmond, VA 23218 s
bec w/encls:
G. Belisle, RII S. Vias, RII L. Engle, NRR Document Control Desk i
NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Fox 78-A Mineral, VA 23117 RII:DRP RII:DRP RII:DRP Ndh GBeli e MSi ue 03/3/93 03/3/93 03/(y/93 A
e 4...
s' l
.f i
ENCLOSURE I P
LIST OF ATTENDEES i
U. S. Nuclear Regulatory Commission E. W. Merschoff, Director, Division of Reactor Projects (DRP), Rcgion II, l
(RII)
A. F. Gibson, Director, Division of Reactor Safety (DRS), RII M. V. Sinkule, Chief, Reactor Projects Branch 2, DRP, RII G. A. Belisle, Chief, Reactor Projects Section 2A, DRP, RII H. N. Berkow, Director, Project Directorate 11-2, Office of Nuclear Reactor Regulation (NRR)
M. Lesser, Senior Resident Inspector, North Anna, DRP, RII M. Branch, Chief, Test Program Section, DRS, RII A. Ruff, Project Engineer, Reactor Projects Section 2A, DRP, RII Virginia Electric & Power Company E. Harrell, Vice President, Nuclear Engineering Services B. Shriver, Assistant Station Manager, North Anna L. Hartz, Manager, Nuclear Quality Assurance J. Smith, Manager, Quality Assurance, North Anna J. Hegner, Supervisor, Nuclear Licensing and Programs l
D. Benson, Manager, Nuclear Engineering P
P t
a
.jk i
l b
l l
i i
}
o i
N i
i
)
N~
Q M
9 m
N M
b Q
D
% $+
4
~
~
eq E
a i
I L3 z
D f
M T
w r
8%s
- 4 i
g Mk h
M I
$m T'
i y*
m$
i h
k%
i 1
~
J i
N
J 1,
n6 a s
n-A.ns a
b 6.,
p 42
-;ig '
l i
s i
a i
i a'
,6 w
I gun -
.O I
i
\\
)
Q* tt p
i 5.a
~
ta*
Q 4
~
As M
ths p
wA I
- N=
&w 4=
.e t
=
Y A,
Q**
==a J
i a
5 4
4 y
%,4 i
=
Y i
m v
=
Y Q
h Q
~
N 2'A; i
7g w
e.
i Q
'4h 9
M
=
't
% 'N CI) i
'"=a a
N i
~-
m i
M t
~
T4k me
==k mh M
a o
- D N
%D4 i
4 m-p-
l se do TP y
s g
u ot a e
l t
ot d
S a
D od h
n s
t o
n s
eA T
o eM e
sis v
lu g
u wd it nl c
e ei ei c
vh d
n jb e
cin o
OR S
F C
Revielv i h ik"ci..<.,n,. :
.: +
.;licalemi Surveilkutce Requinnneufs
' Objectives Review Was initiated in June 1992 Following The Earlier Identification Of A Number Of Errors in ASME XI Pump And Valve Testing And in The Surveillance Of Complex instrument Loops Specific Objectives include:
- Confirm Technical Compliance With All Technical Specification Surveillance Requirements
- Confirm Regulatory Comp!iance With All Technical Specification Surveillance Requirements
- Prepare And Maintain Full Documentation Of Compliance And interpretations
,,. _. _ ~ _.,. - _ _ _ _ _... _. _.
~
e y
c B
n e
d u
e y
q nt a
g e
a i
r o
S t
e
=
l nn o
ed a e i
d r
n o
uA M G n
dt o o h
ea Ti te cm t
o sa M
Po em r
r r
F ur w
wn dof e
e n e
io cI i
v vi t oe cw e
ea r
Rt Pni n
e R
pe pav om ol e
i pR l
l eu e
lll 1
Review AileisMa.
~ 3y' t Goniinned)
- For Each Test Requirement:
l
- Assemble Documentation: Procedures, Drawings, Calculations, Standards, Vendor Information
-Confirm Interpretation Of Requirement
-Confirm Scope: Verify All Components Covered By Requirement Are Addressed
- Verify Test is inclusive And Technically Correct: In The Case Of I&C Or Electrical Circuitry, Verification Will Be From The Origination At The initiator Or Sensor Through All Channels And All Trains Of Relay And Solid-State Circuitry PT0490
Revlew Meilaatlology (continued)
-Verify Action Statement And Mode Change Compliance; Confirm Testing is Consistent With LCO And Action Statement Requirements
-Document Conclusions And Interpretations l
- All Reviews Performed And/Or Reviewed By SRO I
l Qualified Engineer 1
li PTO49 7
... - _..,. _ -. _,. -., _ _ _, _. ~,........,
e 940T P
F O
E T
I G
N A U P
- )SNO I
N T
OW C
E I E TI S
AV D
TE D
SR D
/
RN R
E A
O WI S
T F
OA U
(
PC S
AI T
F NI N
NC E
AE n
M P
io HS t
U T
ip C
L c
O r
R s
D A
e
/
OC D
S NI N
/N O
YH IT R C E
N:
A R
L UT O
U S
T C
I A
L T
A E
C
/
R S
P S
D R
G R
E N
A T
N I
D n
I W
N A
A o
E R
T C
D S
itaic N
E E
r A
la n
F F
e ic b
L C
C f
e m
I N
N L
p E
E E
uN V
R R
S R
E E
in is c
o U
E E
S R
R h
iv c
e e
0 0
0 T
R 1
2 3
!l lI 1111 Il ll ll l
il
e e<o n
M S
I NA F
H O
CTA E S M N GU
/
NTA E
IL T
I G
US N A D
U P E
H CS Y
?. L L
S T. AI T
SR EIA FP S/
IY TL AL N
SU OW F
I E TI AV Y
T E T
SR I
L I
B RN E
A
)s O
C WI I
e u
T L
s O A P
Is P
PC A
n AIF F
pe NI O
O N C E
y n
A E o
D g
P it o
T ip O
lo HS M
r L
c d
R s
o A
e h
O C D
te NI Y
M
/N C
YH R
N e,
C E
p R E U
o c
UT Q
S S
E
(
R E
F CN A
S lL T
R P
E N
M E
B M
O M
C M
n U
o N
E O
it a
C C
ic E
N r
L e
R ic b
U LA A
f N
e m
D I
O L
p u
E N
S E
I N
C V
I T
la n
O R
D c
in io R
U D
h is P
S A
c v
e e
0 0
0 T
R 4
5 6
f l
~
t UNIT PAGE OF SURRY/ NORTH ANNA POWER STATION TECHNICAL SPECIFICATION REVIEW i
Technical Specification:
==
Description:==
Revision Nurnber:
7.0 MARK NUMBERS (List all components affected by this Surveillance);
i i
l l
8.0 COMPUTER POINTS (ERF/ Plant Process):
PREPARED DY:
DATE:
PREPARED BY:
DATE:
APPROVED BY:
DATE:
PT08910
.-..., _- -~
. ~..
. ~. -
i l
f h
1 1
94C TP
~
3 9
9 3
1 9
r 9
e s
1 b
n e
o i
n t
a u
c t
J O
S e
e t
t d
n e n e s
ol ol p
p i
i i
A em em t
t l
l e
po po lu mC mC d
o%
o%
e C0 C0 h
d 6
d 2
c ey ey S
al l
l l
nut ut n
dn nd e
e Aer er h
r h
r h cu ycu t
r rSC rSC o
u
. N*
S*
- l11F l
p L
Findings k - Date North Anna 14 Significant Findings (8 LERs) 7
" Gaps" In The Functional Or Response Time Testing Of Instrument Or Electrical Systems 2
Inadequate Scope, Surveillance Not inclusive Of Population 2
Errors in Technical Specifications 2
Improper Handling Of Action Statements 1
Frequency Error Surry No Major Findings To-Date
-_.-.~_--.-..-_-..-.-_-..--_..-..__..~,,-._..--m.-.
s.----..-__._,----.,_--------__,,-.-
~ _.... - - -,. -.... -,.. ~. _ _. _ _.. -.,,.,.. ~. ~. ~ _., _. _..,,...,. _ - _. -... _....... - -.. - - - _.. _..
Findings Ib - Da!e (Continued)
Findings identified To-Date Were Due To:
- Inattention To Detail in Procedure Development
- Incomplete implementation Of Change Processes
= insufficient Scope And Attention To Detail in Previous Surveillance Reviews Process Changes, Training And Review Methodology Have Been Improved To Prevent Recurrence PT04913
...._,..,_._._..-.m
1 il 4
4 1
9 4D TP g
e n
c d
i l
n l
n o
a rA e
t l
c nt l
i n
evd n
o e
r na Cr e
r c
i uAl p
d u n S
nCa dm A
s ne i
n oio Alp l
d o
aC eim n
it t
i a
ef s
cDO pt ao i
l nC u
i f
pi s
f i
l c
cs a
AaO eue yM n
por o
SrA gl d l
r oio C
ol a
gl owc l
l cia e
irs d
s n
oeR se h
r hi s
t ut e c
ews eda e
Mer Te c u r
i evd eo c
h ed h
r c
TRA TPA
(
l il I
^
E DQ lll:
M 9e D
4 h
E zw
.N W
s m.a 4
W m
2
- t 9&
M*.e y
zZ MM C
w%
M w
w w
N i
mem l
.O t-4
~
~
N~
i
~d
.O h
~ h~ k 4e i
e 3
+k e
o
ro F
yg sde st o
ea l
ct o
oS d
r o
PA h
c o iT t
n t
e o
ae M
mc it n
e n i
e t
a a i
smi f
c e
y r
n D
r e
a Soi t f
r n
d r
eeC i
t Pr r
n b
e gO f;
mir nd e
us a
s P
csd oe n
Ds a
st AAS
i
~
7 1
e do T
P a
m ir e
g t
i n
r i
C s
U d
n s
A e
s ig e
v s
o e
i l
t r
c u
bk e
s n
b e
d
~
j e
b O
s d
a e
si c
r u
o i
e c
eG r
e c
t i
P t
t s
l nsc ey k
a ea L
r n
c m
m nr s
oso f
i d
miPnctiaGt c
i i
l e
r pfodedt rl c
ioleeu Ee e
p m
n gR p
S ri o
e uol ueeUs le PGG BGRNInRn Fo v OOO CCCCCCi e
t PPP RRRRR a
D NNN NNNNN1 S 0t I
I I
l l
1
)
la i
ys tr Be a
i P
dg
(
eo n
sl o
s o
it ed a
s o
r t
s s
h At n
i s
e n
i o
m aM e
t d
i re c
A c
e An o
n t
d l
r a
a P
A nm e
n l
or s
c a
o io n
n c
i i
t tcf o
a g
a n
oi z i
nr t
e a
e l
t o
n uP r
a n
i F
e d
g i
p a
a r
O M
R O
c
i!
1
~
sa ei r
ve it t
i f
cr e
O eC j
b g
r d
u e
On i
i s
f t
c o
Oa p
R t
n m
e e d
S o
s c i
n C
o y
pa m
g s
mr i
o y
oo lo gs Cf r d
oe e
s l
l P
a ou i
h dd e c oo uf l
i te hM dc i
t M
e oe c
Mf Mp i
S i
h c
Example Oj'OperallOm; Melbodology
' Modules A. Control Room Demeanor B. Shift Logs / Records C. ShiftTurnover/ Relief D. System Configuration E. PlantRounds F.
EquipmentLabeling/ Operators Aids G. Control Room Periodic Testing H. Tagging Records / Tagging 1.
Operations Procedures J.. Operations Supervision / Management involvement
r Exanipu qi ni:uhtle Operal1011s Sirpervisosy Arid Mattogeri1esti 1iioolversteitt Modillef Objectives J.1 SRO in The Control Room J13.
Post Accidentinstrumentation J.2 Access Control J14.
Control Room Lighting J.3 SS/SRO Plant Status Awareness J15.
Band Designations J.4 Technical Specification Compliance J16.
Control Board Mimics J.5 Monitoring Significant Evolutions J17.
" Blackboard" Maintenance J.6 ProceduralCompliance J18.
Operating Experience J.7 SRO Alarm Response Oversight J19.
Fuse Control Program J.8 Nuisance Alarms J20.
Goals And Objectives J.9 Supervisory Plant Walkdowns J21.
Managementinterface J.10 Management PlantTours J22.
Correcting Non-Compliances J.11 Management Control Room Evaluations J23.
Overtime Control J.12 Control Room Maintenance And J24.
OperatorAccess Calibration i
mm,
~.
ro t
r l
e o
in vgt h
o r
Onnt iM oWy i
loduC r
el t
e l
nco c v onTni t
e Cl yec v
ar r
e i
eeaef t
t r
sf f r
c aAs eE e
u et o
q "s c n T j
b el ei rNnty?
o t
O d
s Atnielviu i
f f
Q e
bt r
ol a
eeAt uCn r
e st n Ps S l
n t
p E "A o d 'o r
n n
sn a
r t
Oe eAal f
rP a
h R T Ps el x
lepo S
f E
oOvOt r
eT e
n h
nL r
o o o Tssiet C set c
ecicsiad ocvoen
.DAENRA 2
J
Exaniple Qj'Peijkn wuurce Rating Criteria 4
The Number Or Conduct Of Unnecessary Personnel in The Control Room Interfere With Effective Control Of The Plant Which Caused Or Contributed To The
' Significance Of An Event 3
The SRO Normally Controls The Levels Of Unnecessary Personnel in the Control Room But Allows An Excess Of Personnel To Enter During Turnovers, Transients, Start-Up, Or Emergencies PT049 73
.. - ~. - - -,.... _ -, - -. -.. _.,. - - _. - -. _. -
_. - - -. _, -. ~,. -., _ _ _... _
Exanspie Offerjbrutance Rating Criteria (Coutinued) 2 The SRO Occasionally Allows An Accumulation Of Unnecessary Personnel in The Control Room With Some Distraction And Noise But Clears Those Personnel if Noise Levels Are Excessive Or A l
Transient Or Emergency Occurs 1
The SRO Continuously Ensures That The Conduct Or Number Of Unnecessary Personnel in The Control Room Does Not Distract The Reactor i
Operator And Does Not Interfere With Normal Emergency Operations P7049 94
. ~.... _, _.
t
~
n n
e o
m i
t t
c n
ev A
e s
o e
v d
r v
E e
p it n
e m
c A
g c
e I
n x
r r
o i
r E
e o
Tt I
r h
n a
C de t
R O
r ei u
s t
s ss F
e u n e
t c
e e r
ba i
v s
u i
n ei e
r rT r
q t
Mt t
e n
c u
i r
e u d R
oO n
eb q r.
C j
r ea r
l o
bO Rd y
o r
er a
f e
n o
bE r
t l
pc et a t
re en c
al l
P ca bS a
t e
pn cm at f
t e
s e n Ar pe it c o o
e a
c yf cM s
a s l
r r
lue co n
ne FP AT U
UP 0
0 0
0
=
1 2
3 4
i
Perforinance Methodology Process t
- Designate Team Members
- Select Team Leader
- Perform 3 Or More Observations Per Module Objective
- Conduct Team Meeting Each Day To Discuss Observations PT049 M
.. ~.,.
. _.... - _ _ _ - ~... _ _.. ~..... _ ~...,. _,.. _. _....
_...___..___,___.__.___,.___,__.__,._____-._,_,__________________s
FF 9
40 TP s
s g
s n
n e
r i
c e
t o
c a
r n
R P
o n
C g
y i
d s
g e
s o
i A
f r
l i
)
t e
od n
o g
t e
e T
i a
oud g
n I
nn n
a i
n M
i i
t t
enO ee MCn Mi o
o ev n
t o
c t
t t
i e(
i e
r a
r c
s mj o
t o
i n
v ab p
S p
eO e
o e
r a
e T
R T
R m
p t h u
cc e
t S
ua r
n h
ro dE a
e s
i f
f e
n p
s lb r
r e
e i
oo r
r u
r e
B CF P
P P
P
.ll j
i
52
~
e s
o T
P p
o le s
~
v e
e
~
e d
v D
a t
~
i Mm c
s d
t e
e l
n et b
j u
A r
s Ay O
s t
e sS n
r o
t R
p ng O
e ein p
y g
R mk U 0 c
w2 o
w n
a e
gr n
l iT o a o
i s
d v
l h
e sl l
a oT o
R An F
r r
h l
s ae se t
e n n nn mt t
t t
a M
ela eI r
e or mP mh t
t g
rG f
r n
r u
e d ao a o Pe pi pr t
t ec eh Aa DA DT QR
l
?
l Norib Ainta Oualliy. assn a:.we Radiological l
Protection Follow-Up Assessnient Jan 91 Oct 91 Objective Rating Rating C.5 Use Of Proper Personnel Frisking Techniques 2.5 1.5 C.6 Personnel Frisking After Leaving Contaminated Areas 2.5 1.0 J.9 Control, Receipt And Acknowledgement Of Visitor Doses 3.0 1.0 M.3 Survey Of Badges For Contamination 2.5 1.0 S.4 Control Of Non-RCA Tools And Equipment To 2.5 2.0 Prevent Contamination S.6 Control Of RCA Tools And Equipment To Minimize 2.5 3.5 Waste Generation Average 2.6 1.7 1.0 Fully Acceptable - Meets Or Exceeds Performance Objectives 2.0 Acceptable - Requires Further improvement To Meet Standard 3.0 Unsatisfactory-Requires Corrective Action 4.0 Unacceptable - Contributed To An Event, Personnel Error Or Transient PT049 29
.1
M 901 1
1 1
1 22 899999999 999999999 1
1 1
1 1
1 1
1 1
t gycnt cgt d
p uaea c
c e AMDJODAeuO e
S us s
i p
s U
i r
w a
o l
p o
l e
F h
ppnn y
UUoo i
i g
wwtcc t
o ooee l
t t
l l
o oo oo l
l d
FF P P
)l r
r
)
o l
eeel a
a l
h cccaai i
t s
ccr st t
e n nnniiana r
o aaagg M
i n n n o o (P o P it (
t eeel l
at t
t a
ooArA r
nnnii eiiidd e
p a a a a a & p&
OMMMRROOO l
l lllL
~[y
~
l l
fib b d?5]? 4 !!,'ti:ld)lTj'(YS$$5Y i
Fully Ac.ceptable 1 --
1.2 i
1.3 1.3 1.6 1.7 1.7 1.7 Acceptable 2 -
2.
Unsatisfactory 3 -
Operations Maintenance Radioloclical Industrial Protect on Safety Previous SALP
. Current SALP l
l Pio4e at E
-