ML20050D487
| ML20050D487 | |
| Person / Time | |
|---|---|
| Site: | Cooper |
| Issue date: | 03/25/1982 |
| From: | Boardman J, Crossman W, Randy Hall, Murphy M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050D473 | List: |
| References | |
| 50-298-82-04, 50-298-82-4, NUDOCS 8204120252 | |
| Download: ML20050D487 (10) | |
See also: IR 05000298/1982004
Text
.
APPENDIX B
U. S. NUCLEAR REGULATORY COMMISION
REGION IV
Report No. 50-298/82-04
Docket No. 50-298
License No. DPR-46
Licensee:
Nebraska Public Power District
P. O. Box 499
Columbus, Nebraska 68601
facility Name:
Cooper Nuclear Station
Inspection At:
Cooper Nuclear Station
Inspection Conducted:
February 8-12, 1982
Inspectors:
// )
W
MM
D
J[ /t.' Boardman, Reactor Inspector
Date
RMctor Project Section B (Paras.1,2,3,4,7)
'
'
D/
L
M. E. Murphy,' Reactor Jhspector
'
Date
'
Reactor Project Section C (Paras. 1,5,6)
Approved:
/u'6[
SM'f'!82
W. A. Crossman, Chief
Date
Reactor Project Section B
.
3
fW
"
R. E. riall, Ctiief
/
D[te
Reactor Project Section C
Inspection Summary
Inspection Conducted During The Period of February 8-12, 1982
(Report 50-298/82-04)
Areas Inspected:
Routine, unannounced inspection including procedures; procure-
ment activities related to material requisitioning, receipt, storage, and
identification; controls for test and measuring requirement; and control and
evaluation of surveillance testing, calibration, and inspection.
The inspection
involved 68 inspector-hours on site by two NRC inspectors.
8204120252 820331
DR ADOCK 05000298
)
r-
.
2
Results:
In the four areas inspected, no violations were identified in three
areas, and one apparent violation was identified in the fourth area (violation -
failure to have documented procedures
paragraph 3)
!
i
<
4
.
3
Details
1.
Persons Contacted
P. Borer, Engineering Supervisor
B. Brungardt, Surveillance Coordinator
C. Goebel, Administrative Supervisor
H. Jantzen, I&C Supervisor
L. Lawrence, Maintenance Supervisor
D. Majeres, Maintenance Planner
- G. Smith, Quality Assurance Specialist
D. Norvell, Electrical Supervisor
- P. Thomason, Acting Operations Supervisor
- D. Whitman, Technical Assistant to the Station Superintendent
- Present at Exit Interview.
The NRC inspectors also contacted other licensee personnel, including
clerical, administrative, and maintenance personnel.
2.
Licensee Action on Previous Inspection Findings
(Closed) Open item (8106-02).
The licensee had not required an
engineering review of documentation of material conformance.
This review
is now included in licensee Administrative Procedure 1.11, Revision 17,
" Requisitioning, Receiving, Storage of Essential Parts and Components."
(Closed) Violation (8106-01).
Licensee receiving reports were not being
signed as being inspected and "CNS Stores Requisitions" were not properly
completed as required by CNS Administrative Procedure 1.11, Revision 16.
A review of 20 receiving reports and 75 "CNS Store's Requisitions"
revealed no further problems in this area.
3.
Material Procurement, Receipt, Storage, and Handling
The NRC inspector reviewed the licensee's program and implementing proceduras
for receipt, storage, and control of equipment and materials, including
repair parts, for compliance with Appendix B to Part 50 of Title 10, Code
of Federal Regulations and " Cooper Nuclear Station Quality Assurance
Program for Operation," Revision 8, dated August 20, 1979.
A review of stored material revealed the following apparent problems with
squibs (primers) used in explosive (shear) valves for the Standby Liquid
Control (SLC) System and the Transversing In-Core Probe (TIP) System.
a.
Licensee Administrative Procedure 1.11, Section 1.11.5.4.3 requires
storage of hazardous essential material and parts in accordance with
Administrative Procedure 1.6.8.
Squibs purchased on order 133738
- .
m
O
4
were marked " Class C Explosives" with a Department of Transportation
(DOT) hazardous material label, but were not covered by the licensee
procedure 1.6, " Personnel and Equipment Safety," section 1.6.8,
" Hazardous Material Control." Squibs included as stored material
on licensee purchase orders 45338, 129388, and 174065 were not
identified as hazardous material.
This will remain an open item
until the licensee has verified that his procedures and control of
these squibs as hazardous material are adequate (8204-02).
b.
The three remaining squibs purchased on licensee order 174065 are
marked " MFD 2/81," indicating that they were manufactured in February
1981, and the licensee's shelf life control is based on that date.
The squibs are also marked with the lot number " HEC 80J005-001."
The official records for Purchase Order 174065 contain lot
acceptance test reports for lot HEC 80J005-001 stating that this lot
was tested September 16, 1980, 5 months before the indicated manufac-
turing date.
The remaining squib on licensee order 129388 is marked
with a manufacture date of October 1977.
There is no supplier docu-
mentation of this manufacturing date or of the test date, only a
certificate of compliance.
(The licensee also tested a squib on this
order.) This will remain an open item until the licensee has
obtained verification of the manufacturing dates of the subject squibs
(8204-03).
A squib on order 174065 is installed in Train A and a squib on order
129388 is installed in Train B of the SLC system.
Weaknesses in the licensees identification and handling of essential
components, materials, and parts requiring shelf life control was
identified in NRC Inspection Report 50-298/81-06.
The licensee has
made some progress in establishing a computer program for shelf life
control, but has not established a formal, documented program of
shelf life control.
10 CFR Part 50, Appendix B, Criterion V, requires that activities
affecting quality shall be prescribed by documented instructions or
procedures.
The " Cooper Nuclear Station Quality Assurance Program for
Operation," Revision 8, dated August 20, 1979, sections 2.4 and 2.5,
state that quality assurance activities and other activities which
have nuclear safety significance will be prescribed by documented
instructions or procedures and specifically that licensee procedures
shall include provisions for assuring that necessary quality
requirements are incorporated directly into purchase orders and
contracts for essential spare parts, material, and equipment shall
also include provisions for assuring that necessary records are
supplied to the purchaser by the supplier.
>
-
.
5
Licensee Administrative Procedure 1.11, Revision 17,
" Requisitioning, Receiving, Storage of Essential Parts and
Components," dated December 8, 1981, does not require identification
of shelf life requirements, documentation of shelf life from
suppliers, or control of shelf life after receipt of material
requiring this control.
Failure to prescribe activities affecting quality in documented
instructions or procedures is an apparent violation of 10 CFR Part 50, Appendix B, Criterion V (8204-01).
4.
Procedures
The inspector reviewed the following licensee approved procedures for
compliance with regulatory requirements, including Technical
Specification requirements, and with " Cooper Nuclear Station Quality
_
Assurance Program for Operation," Revision 8, dated August 20, 1979, and
for apparent technical adequacy.
Procedure
Approval
Number
Title
Revision
Date
Administrative
1. 3
Procedures
6
2/26/81
1.10
Nonconformance and Corrective
Action
12
3/16/81
1.11
Requisitioning, Receiving, Storage
of Essential Parts and Components
17
12/8/81
General Operating Procedures
2.1.2
Hot Start-up Procedure
14
10/9/81
2.1.15
Reactor Recirc Pump Operation
9
3/3/80
System Operating Procedures
2.2.1
Automatic Depressurization System
14
11/19/81
2.2.67
Reactor Core Isolation Cooling
18
11/18/81
2.2.68
Reactor Recirculation System
19
1/22/82
2.2.74
Standby Liquid Control System
12
5/4/81
Alarm Procedures
2.3.2.21
6
6/9/80
2.3.2.24
8
10/15/80
2.3.2.25
8
4/9/81
2.3.2.26
Panel 9-4, Annunicator 9-4-3
6
11/6/80
2.3.2.28
Panel 9-5, Annunicator 9-5-2
7
10/3/81
a
6
Procedure
Approval
Number
Title
Revision
Date
Abnormal Procedures
2.4.2.2.3
Recirc Pump A or 8 Seal Failure
2
10/5/81
2.4.2.2.4
Reactor Vessel Cold Water Stratifi-
cation
3
2/22/78
2.4.2.2.5
JET Pump Flow Failure
3
8/28/81
2.4.2.3.1
Relief Valves Stuck Open
10
8/28/81
2.4.2.3.1
Relief Valve Inoptrable
4
6/2/80
Surveillance Procedure
6.3.8.4
SLC Manual Initiation Test Tank to RV 8
10/21/81
Maintenance Procedure
7.2.22
Main Steam SRVs Periodic Testing,
Inspection, Removal & Installation
6
10/5/81
7.2.25
Standby Liquid control System
Explosive (Squib) Valve Insert
Replacement
4
3/19/80
7.2.49
Inspection and Repair of ASCO
0
1/12/81
7.2.50
Limitorque SMB Valve Operators
Removal, Overhaul, and Replacement
1
12/17/81
Quality Assurance Instructions (QAI)
QAI-9
Guidelines for Establishing Quality
Classifications of Components and
Materials
7
6/1/81
Quality Assurance Plan (QAP)
QAP-1400
Procurement and Control of Essential
Spare Parts, Materials and
Equipment
10
10/3/80
No deviations or violations were identified; however, System Operating
Procedure 2.2.67, section VII.H, step 27, page 18, states " Ensure system
is in a standby configuration as per section VIII.A, steps 1. through 10."
There is no section VIII; this apparently should read "section VII."
_ _ _ . _ _
-
F-
.
7
The NRC inspector noted that Administrative Procedure 1.11,
Section 1.11.3.1.1, requires the use of the guidelines established by
CNS Instruction letter #75-1 for determination of classification of
essential parts, equipment, and materials in lieu of Table 1 of " Cooper
Nuclear Station Quality Assurance Program for Operations" in addition,
QAI-9, Revision 7, dated May 1,1981, " Guidelines for Establishing
Quality Classifications of Conponents and Materials" provides necessary
details not covered by Table 1, but is not invoked by Admininistrative
Procedure 1.11.
This will remain an open item until Administrative
Procedure 1.11 has been revised to incorporate the latest licensee require-
ments for identification of essential items (8204-04).
It is further noted by the NRC inspector that Administrative Procedure 1.3,
" Procedures," does not require a review of procedures to assure compliance
with 10 CFR Part 50.59, nor is there documentation of such a raview.
Licensee personnel stated that procedure review by the Station Operations
Review Committee (50RC) per se constitutes the required 10 CFR Part 50.59
review and that specific cerIIfication is not considered necessary.
5.
Surveillance Testing, Calibration Control, Test and Measurement
Equipment Programs
The purpose of this inspection was to review the licensee's program for
surveillance testing and calibration control for plant process and
test and measurement equipment.
This review was to verify that the
licensee's programs as developed and implemented conform to the
requirements of technical specifications section 4, 10 CFR 50.55(a) and
(g), Regulatory Guide 1.33 and IEEE 336.
The scope of this inspection included discussions with technicians,
supervisory, and coordination personnel, review of surveillance testing
and calibration schedules, logs, and status reports, and the review of the
following records and procedures:
Test instrument data records for Test Instruments 15-1793, 15-2514,
15-2541, 15-2633, and 15-2682, and Nonconformance Report 002338.
.
8
Procedure
Approval
Number
Title
Revision
Date
Comments
6.2.2.16
CSCS Discharge Piping Full Low
Pressure Alarm Calibration and
Functional Test
7
6/6/81
Note 1
6.2.2.2.1
ADS Water Level Calibration and
Functional / Functional Test
13
6/25/81 Note 1
6.2.2.2.3
ADS Timer Calibration and Actuation
Functional Test
14
10/3/80 Note 1
6.2.2.3.6
HPCI Pump Low Suction Pressure
Calibration and Functional /Func-
tional Test
8
8/4/80
Note 1
7.1. 2
Calibration Procedure for Test
Equipment
5
7/13/81 Note 2
7.5.4.1
Manometer Inspection and Maintenance
Procedure
8
12/24/81 Note 2
7.5.4.2
Pressure Test Gauge Calibration
14
7/21/81 Note 2
7.5.4.3
Deadweight Pressure Tester Calibra-
tion Procedure
5
5/1/81
Note 2
7.5.4.4
Mean Square Voltage / Wide Range
Monitor Test Alternator Calibration
Procedure
3
4/28/81 Note 2
7.5.4.5
Emergency Core Cooling System Test
Switch Maintenance
0
7/2/80
Note 2
Notes:
1.
Reviewed Surveillance Testing and Calibration Data Sheets for
these surveillance procedures.
2.
Reviewed these procedures.
No items of noncompliance or deviations were identified.
6.
Barge Traffic
Paragraph 5.7 of the technical specifications states:
" Barge traffic on the Missouri River past the site has been analyzed to
determine that the present size and cargo materials do not create a hazard
to the safe operation of the plant.
Contact will be maintained with the
Corps of Engineers to determine if and when additional analyses are
required due to changes in barge size or cargo."
}
,___
i
.
9
The NRC inspector discussed this requirement with a licensee representative
and determined that a memo to the Corps of Engineers from the station
superintendent dated April 24, 1980, was on file.
There was no apparent
response and this appears to be the only contact since the original
requirement in 1973/74.
The NRC inspector voiced concern over the apparent
lack of response and follow-up.
The licensee's representative said that
this would be investigated.
This will remain an open item pending licensee's
resolution (8204-05).
7.
Exit Interview
An exit interview was conducted on February 12, 1982, with those NPPD
personnel denoted in paragraph 1 of this report to summarize the scope of
the inspection and the findings.
!
,
,
e
NmcFOmo796
U.S. NUCLEAR F;EGULATOWY COMMISSION
PeacPAL iNsPECTOa tNew mer. *st ara 'wie avem
U mm
SoA RDM A S) ' k k Q
Y
INSPECTOR'S REPORT
, , , , ,
Office of Inspection and Enforcement
M/ A . C/2OSsMAM
" " ' ' " ' T, I;L. SoA R DM A A)
A1. e M Mt2 t*H Y
78 ANS ACTION
REPOa7
NEAT INSPEC OATE
L8CEN$EElvENOOm
DOCKET NO 'S eets OA UCENSE
NO.8vPaODUCTH13agtse
NO
SEQ
MO
vn
M dtfAsto, Ar.I,c Po ~rr<t Dica, C.r- d ' - * * ' "
o 5 o o o 1
9 ?
I
? 2 o u
A
M - MOO'FV
,
D - OELETE
C
-
D
R - SEPLACE
'
..
aEaOD OF iNvE STIGA TION e tN5PF CTON
- NSPECTION PERF08ME D Sy
ORGANaZATON CODE OF REGIONIMQ CONDUCT.
F#O4
TO
[
t
mEGONAL OFF#CE STAFF
OTMER
_
y
,,
p
40
OAv l va
MO
OAv
vs
2 mE510ENf 6NSPECTOn
aEGON
DNiSON
9AANCH
$
l
C
l
A
23
()l-), o RI?ll O!2. il1 tl 2.,
2 Pf aFOaMANCE APPa AisAL TE AM
emenwmmra m acw wgw m m 15an=ganm w u m:tma
ry ungp g
-
__ m
TY PE OF ACTiviT v CONOUCT ED iCheca are Oos oreve
aEGONAL ACTION
""
/
02 - S AFETY
06 - MGMT visit
to PLANT SEC.
14 - lNOUIRY
1 - NRC FOAM 591
03 INCIDENT
07 - $PECIAL
11 - INVENT VER.
?$ - iNVE5flGATION
2 mEGIONAL OFFICE LETTER
04 - ENFOnCEMENT
00 - VENDOR
12 - SHIPMENT EXPORT
05 - MGMT AUDIT
09 - MAT ACCT
9 3. iM POn i
I
.
' Air s
- '
=
.hi .
ums- s %'d.di, ' [.
p S .. * - '
- A
.#,
'
.
.
bw
f 0T AL NUM0ER
ENFORCEMENT CONFERENCE
atPOR T CONT AiN 2 N
LETTEa On aEPORT TR AN5 MITT AL DATE
%
tw.,
. vt
e<
OF viOLAT10NS ANO
- ELO
iNFOR M A TION
A
e
C
o
OEylATONS
NRC FOAM 591
mEPORTSENT
1 - CLEAR
On MEG.
TOwo FOm
LETTERe55UEO
ACTON
fX
2 - votATioN
l OAV lva
MO
DAY l v4
fS lC
D
Al8
C
D
A
8
C
D
uO
3 - DEviA' ION
A
4 - voLAf oN 4 0EviaroN
g,p;
j
j
i vE5
t - vEs
$ j'$lf p/1 jl
l l l
,
,
,
1"ENF?Ne@ ,' a O n 8 K'. M L: 2 2 2:: d d '
M
, - .. . e:
a.
3
r
MODULE iNsOaM A riON
woout E iNsoava rioN
MODULE REQ FOLLOWUP
.5,
MODULE NUMBER INSP
8h
MODULE aEQ. FOLLOWUP
yg!y
MODULE NUMBEM INSP
ggly
ie
r
r
si a
ie
r
55 55
hr*5
-
- :
}
0-
ra
1
s
!
8:
!.
8
- :
85
5:c
u--,a.
3 :t :,
-
-
.
.
.<
.- g.
8
<
3 t
.
-
a
a
>
.
> t
-
-
-
.
.
8
%
C 2
<
$3
- E
_
.
.
.
8
in
- Kary
.
-
o
7
-5=rs aao
i
<g
=
I 15
!
- n g hasa,
r8e
I
= 5
t!
- 3
I
=i <5 : !
2
<
<
!
3
a <
y2
<
<
2
E
<
Ls:s
r8e
I
su
!
-
,
i
liil
Qi f l /i tis 1-
si bpi l-
3,' S
oiliS Di 7i.5
liil
o
3
^
o o,2
, ,
i
'
e
i
i
.
i
,
liil
liil
"
'
i i
i i
i
i i
i i
i
1
,,
i l
i
i i
i i
l l
l
l i
liil
Ii,1
o
c
, i
, ,
i
, ,
, ,
,
lo,lV o,fia
i
i
?s9,2.17, o,6 l-
opie
Iiii
V5 3,317 0 01-
^
A
i
i
i i
e
,,
i
.
i
li,
liiI
I,iI
'
, ,
,
i i
i i
i
Iiit
I,,1
c
=
i ,
i ,
i
i ,
, ,
,
!
l,!,,1
I,,1
o
=
,,
, ,
,
s i
. .
T h zl? oici-
Iiii
d I,70 $,0
IiiI
IiiI
'
-
i
,
e
i
i
i i
i i
i
.
i
Iiil
i i
i i
i iiil
'
a
i i
, i
i
li,I
ii,I
"
c
, ,
, i
i
, ,
, i
i
lj
i.,il
_
i
i
,
'
! !
, !
,
,f
, i
'
' 1
, !
..
!
F
i
l i
'
! ,
, !
i
i !
i
l
! i
i i
i i
l
i i
i i ,1
l,,1
-
e
, ,
, ,
,
, ,
, ,
,
d
l
liil
-
ii
, i
i liiI
i i
i i
1
1
. _ , _ _ , . .
< u n ' oN - e 4 s i4 r oN
g g
g g
g
l
l
l g
9 g
9
l l
ilnl+tw , m m H + m
ext.
,o= w - e =. ,1 >l A isc .# 4
- , w woe.+ o n-x.
j
.-.
.
E 'o"= * *
occxer ,.oas e,2.ica uctase
"<'o"7
"couta=vuesa
gy ; .w
fi3:2OOi
!- iV#5 *
'[,8j'y
NO.ggy emoovCv)(13 cqnes
NO.
SEO.
O
INSPECTOR'S REPORT
0 Y O C o I t 8
? 2.10 4
a
- "*'*""**'ic"
,,$' i3
(Continuation)
$4c-
.
3
.
,
e
Office of Inspection and Enforcement
7
p
_,
e e
_
C
..ou r e,, on oe u re,. w-- .,o e uno arauw. e .-n
- a e. ~n .~
o. ** ~. * -= o. -
,=o-.o-
m ~ wuan-uw..an>
h
/n cp2 Parer 50,. APPEAIDix B, cairrittor) IJ,. rn e
rnAstr2A R Y TO
s
t i et=~Airf-G
CA a s-n 'Tb
PResciaiRn
A CTIvo r/ L=%
A (=ns crt AJG-
Oli A Li TV
IN Da e ux1a AITu n
Pt2a cenu i?2s
5
i
.
h
7
.
9
50
11
12.
11
to
18k
il
17
=
.g
19
_
20.
1
21
i
z=
ri l
,
24
l
"
.
.
??
'1
.
!
a
e
i
19
n
L1
.
1
u.
i
E
4i
.
- !
,
<
,
.
U.S. NUCLEAR REGULATORY COMMISSION