IR 05000298/1982021
| ML20027B216 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/30/1982 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20027B209 | List: |
| References | |
| 50-298-82-21, NUDOCS 8209160540 | |
| Download: ML20027B216 (8) | |
Text
.
.
APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-298/82-21 Docket:
50-298 Licensee: Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted: July 1-31, 1982 TIS 3-L.
fhoM2.
Inspector:
D. L. DuBois, Resident Reactor Date Inspector, Reactor Project Section A Approved:
7'
.
T/Ja/81-T. F. Westerman, Chief
/ Date Reactor Project Section A Inspection Summary Inspection Conducted July 1-31, 1982 (Report 50-298/82-21)
Areas Inspected:
Routine, announced inspection of operational safety verifications, monthly surveillance observations, core power distribution limits surveillance, local power range monitor system calibration, average power range monitor system calibration, core thermal power evaluation, and review of plant operations. This inspection involved 44 inspector-hours onsite by one NRC inspector.
Results: Within the areas inspected no violations or deviations were identified.
8209160540 820901 PDR ADOCK 05000298 O
.
-
DETAILS 1.
Persons Contacted
- L. Lessor, Plant Superintendent
- P. Thomason, Acting Operations Supervisor V. Wolstenholm, QA Supervisor P. Ballinger, Reactor Engineer R. Brungardt, Surveillance Planner
- Indicates presence at exit meetings.
2.
Operational Safety Verification The NRC inspector observed control room operations, instrumentation, controls, reviewed applicable logs, and conducted discussions with control room operators.
The NRC inspector verified operability of:
Automatic Depressurization System
'A' Core Spray System Standby Liquid Control System 4160 V Emergency Power System The NRC inspector reviewed safety clearance records, including verification that affected components were removed from and returned to service in a correct and approved manner, that redundant equipment was verified operable, and that limiting conditions for operation were adequately identified and maintained. The NRC inspector also verified that maintenance requests had been initiated for equipment discovered to require repair or routine preventive upkeep, appropriate priority was assigned, and maintenance commenced in a timely manner commensurate with assigned priorities.
Tours of accessible areas of the facility were conducted to observe normal security practices, plant and equipment ;or Jitions, including Cleanliness, radiological controls, fire suppression i n tems, emergency equipment, potential fire hacards, fluid leaks, excessive vibration and instrumentation adequacy.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Specification, 10 CFR. and Administrative Procedures.
No violations or deviations were identified in these areas.
3.
Monthly Surveillance Observations The NRC inspector observed portions of Technical Specification required surveillance tests to verify that testing was performed in accordance with adequate procedures; test instrumentation was in calibration; limiting conditions for operation were met; removal and subsequent restoration of affected components was accomplished; test results conformed with
_
_
.
.
__.
.
Technical Specification and procedure requirements; tests were reviewed by personnel other than the person directing the test; and deficiencies identi-fied during testing were properly reviewed and resolved by appropriate management personnel.
The following Surveillance Tests were selected and observed:
,
6.3.2.1 - Auto Depressurization System Manual Valve Actuation 6.3.3.1 - High Pressure Coolant Injection System Test Mode Surveillance 6.3.3.4 - High Pressure Coolant Injection System Pump Operability
6.3.6.4 - Reactor Core Isolation Cooling System Pump Operability 10.1
- Average Power Range Monitor System Calibration These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Specification, 10 CFR, and Administrative Procedures.
No violations or deviations were identified in these areas.
>
4.
Core Power Distribution Limits Surveillance The NRC inspector conducted discussions with CNS reactor engineers, reviewed records and data relevant to local power range monitor system (LPRM)
calibrations and core performance evaluations conducted July 9,1982, and July 20, 1982. The review and discussions included the following:
,
a.
Verification that the linear heat generation rate (LHGR), core maximum peaking factors (CMPF), minimum critical power ratio (MCPR), and average planar linear heat generation rate (APLHGR) were within prescribed limits.
i b.
Examination of LPRM and BASE distribution calculations as typed out by the 00-1, "LPRM Calibration and Base Data," on-demand typewriter.
Typed alarms, errors, and other in-process messages were also reviewed.'
c.
Verification that TIP (Traversing Incore Probe) machine normalization factors were properly obtained.
d.
Examination of licensee procedures for ascertaining operation within licensed limits, should the process computer become unavailable.
e.
Verification that the plant computer memory was updated per OD-15,
" Computer Shutdown and Outage Recovery Monitor," following a period of plant operation during which the computer was out-of-service.
f.
Verification that average power range monitor channel gains were adjusted as necessary following an LPRM calibration, or as otherwise required by the Technical Specification.
.. _ - - -
..-
. _-
-
-
.
.
.
-..-
_
-
g.
Verification that the computer received and acce.ced all data, resulting from TIP traces, LPRM calibration, and APRM gain changes.
The following licensee procedures were reviewed:
10.3 - Core Thermal Power Evaluation, Rev. 4, dated Ma oh 3, 1981 10.4' - Core Thermal Hydraulic Evaluation, Rev. 6, dated February 28,-1979 10.7 - Maximum APLHGR and Local LHGR, Rev. 7, dated May 30, 1979 10.17 - Process Computer Beginning of Cycle Data Update, Rev. 1, dated December 17, 1981 The following computer printouts dated July 9, 1982, and July 20, 1982, were reviewed:
P-1
- Periodic Core Performance Logs 00-1 - Whole-Core LPRM Calibration and Base Distributions OD-3 - Core Thermal Power and APRM Calibration 0D-6 - Thermal Data Specified Fuel Bundles OD-7 - Present Control Rod Positions OD-8 - Present LPRM Readings OD-13 - LPRM Sensitivity 0D-16 - Target Exposure and Power Data These reviews and discussions were conducted to verify that the plant is being operated within licensed power distribution limits.
!
I No violations or deviations were identified in these areas.
5.
Local Power Range Monitor System Calibration i
The NRC inspector reviewed records and procedures applicable to calibrations of the local power range monitor system (LPRM) which were performed on July 9 and 15, 1902.
Included in the review were verifications of the following:
a.
Performance of traversing incore probe system (TIP) intercalibration scans and core flux mapping.
b.
Accurate determination of individual LPRM calibration currents;
!
calibration constants, and amplifier gain adjustment factors.
c.
Reactor thermal power was maintained within prescribed limits and control rod movement did not occur during the performance of the LPRM calibrations.
d.
All LPRM ^+ actor readings were obtained prior to and following LPRM amplifie
.n adjustment.
e.
Average power range monitor (APRM) channel recalibration followed the affected APRM chdnnel(s) associated LPRM group adjustments.
l l
.
_. ~.
_ _ _
.
.
.
.
f.
LPRM calibrations have occurred at the required frequency.
The following CNS procedures were reviewed for technical adequacy:
10.5 - LPRM Calibration or BASE Distribution Update, Rev. 15, dated February 20, 1981 i
10.15 - TIP Reproducibility and Core Power Symmetry Test (B0L),
Rev. 2, dated September 23, 1980 t
These reviews were performed to verify that calibration of the LPRM System was performed in accordance with approved procedures and that the APRM System was re-calibrated following any applicable LPRM adjustments.
No violations or deviations were identified in these areas.
6.
Average Power Range Monitor System Calibration The NRC inspector reviewed licensee records and held discussions with personnel applicable to calibration of the average power range monitor system (APRM).
Included in the review were the following:
a.
Verification that control rod positions and reactor recirculation flow were held as constant as possible during data collection.
b.
Verification that APRM amplifier gains were adjusted to indicate the percent of rated power calculated by a heat balance.
CNS Procedure 10.1, titled "APRM Calibration," Rev.12, dated June 29, 1982, was reviewed for technical adequacy.
These reviews and discussions were conducted to verify that the APRM system was properly calibrated to actual core thermal power using technically adequate and approved procedures.
No violations or deviations were identified in these areas.
7.
Core Thermal Power Evaluation The NRC inspector reviewed licensee records, data sheets, and procedures applicable to reactor core thermal power evaluation and performance, which were conducted July 9 and 15, 1982.
The NRC inspector verified that procedure prerequisites were met prior to performing a core performance evaluation, that calculations were correct, and that the frequency of evaluation met the requirements of the CNS Technical Specification.
~
The following CNS procedures were reviewed for technical adequacy:
'T-4
- -, - -
-
- - -
_+, - - -
e
--
.m
,.> --
,
--
,-., -
--
r -,,..,
.
.
10.3 - Core Thermal Power Evaluation, Rev. 4, dated March 3, 1981 10.18 - Routine Core Performance Data Gathering, Rev. 1, dated December 20, 1978 10.19 - Guide For 0D-1 and OD-2 Utilization, Rev.1, dated February 28, 1979 No violations or deviations were identified in these areas.
8.
Review of Plant Operations The NRC inspector reviewed the following CNS administrative and startup procedures:
1.3
- Procedures, Rev. 8, dated March 12, 1982 1.4
- Station Rules of Practice, Rev. 45, dated July 9,1982 1.6
- Personnel and Equipment Safety, Rev. 23, dated July 9,1982 1.16 - Hydrostatic / Leak Test, Rev. 6, dated February 19, 1982 2.1.1 - Cold Startup Procedure, Rev. 32, dated May 14, 1982 Prior to plant startup, the NRC inspector performed the following systems lineup verifications:
'A' Core Spray System 4160 V Emergency Power System
'A'
and 'B'
RHR Systems *
Reactor Feedwater System *
- Inside Primary Containment Only The NRC inspector observed two separate plant startups that occurred July 7, 1982, and July 15, 1982.
!
These reviews, system verifications, and observations were performed to ensure adequacy of the licensee's administrative controls, startup procedures, and system checklists which are used for returning safety-related systems to an operating status following maintenance, modification, or testing.
No violations or deviations were identified in these areas.
l 9.
Exit Meetings l
Exit meetings were conducted at the conclusion of each portion of the inspection. The plant superintendent was informed of the above findings.
l l
i l
l l
l i
!
>
Sheet 1 of 2 U.S. NUCLEAR REGULATORY COMMISSION
,N,RC FORJ 70s
-
PRINCIPI.L WSPECTOR Nm.asr erse avmme are t
ien
,E uC om
.
DuBois. Dennis L.
INSPECTOR'S REPORT REv, EWER Office of Inspection and Enforcement Westerman, Thomas F.
iNSPECTOES D. L. DuBois
'"^*5,^c'**
cOCnET NO <8.,.OR uCENSE
"' 'o "
N"'*Sc " '
uCEN$wvENDOR 1,
NO 18v PRODUCTH13.tm No Sao MO vm
' - *5' "
Nebr. Public Power District X
n s o n n 9 o
R R
?
?
- -" "
P. O. Sox 499
"
_
cnitimt, L NF.
6ft601
_
D - DELETE C
R REPLACE D
2
16
PE iOD OF INVEST GATIONnNSPECTON INSPECTION PER FORMED 8v ORGANt2ATON COCE OF REGION /HQ CONDUCT-
'"
'I',*me>"'#
)OTHER F OM TO 1 - REGIONAL OFFICE STAFF m-wee.v u,~ a m n,
X 2 - aESIDENT INSPECTOR
,_._M eCN
.
OfV SON
MO.
DJ.y vm YO DAY va 017 011 8l2 Ol7 311 81 2 2-""'0"*^*c""^'5^'"**
l
_
SRAN&
'
'
C I
a
25
31 32 -
i
l
REGIONAL ACTION TYPE OF ACTivtTv CONDUCTED iCheo one ton onsvi ICheck one bon oarvi Y
02 - SAFETY
_
06 - MGMT VISIT
_
10 - PLANT SEC.
14 - 'NQUtRY
_
1 - N1C FORM 591 03 - INCIDENT 07 - SPECIAL 11 - INVENT.VER 15 - INVESTIGATION
{
2 - KEGONAL OFFICE LETTER 04 - ENFORCEMENT 08 - VENDOR 12 - SHIPMENT / EXPORT 05 - MGMT. AUDsT 09 - MAT. ACCT.
13 - eM POR T
37-38
.Np kGTeO4 sNw E 5TiGAT.GN FiNaiNGs TCT AL NUMBER ENFORCEMENT CONFERENCE REPORT CONTAiN 2 No LETTER OP REPO1T TR ANSM'TTA. DATE
" *
CF VOLATIONS AND MELD INFOR M A TION A
C D
DCVIATONS NaC FCRPA 591 REPORT SENT
_
OR REG TCHQFOR LE TT E R IS iUE D AC?iCN 2 - VIOLATON 3 - DEvsATION A
B l C D
Al8lCl0l lYR YO lDAV lYR A
B C
D MO DAY 4 - viOLATON & DEVIATCN j
j j j l 1 VES t - vf 5
'$@
1@M l l !l l
,
,
,
,
4041
43
59
55 MODULE INFORM ATION MOOut f +NFeaMATCN
$6.h MODULE NUV8ER INSP yg 9 MODULE REO. FOLLOWUP
$6,h MODULE NUM9ER INSP 0g 9 VODULE REQ FOLLOWUP El r
r HE5 i e r
$
a h!$g 3 e r
3:d$-5
-
- 5 a=
- t 5 8=
5 5 a=
a=
6 Ijis$ h:i ~-! I !E
st !
5 !I 5!
s 6 !!5Es i5=
$ N !!
i
,,
s n
=
E 5 3 35
s ;
a a
s I :i 5 E3
- : E s-aca r82
I s5 i s
- s I s5
!!
E as:z r82 c
= u is
i 5 3iOl7,0i3l 010,5 e i i
ll l8 5 6tll7i0i6l Oioi2 Di6is c i
ll t I
^
^
i i
l, l
i e i t i
i i
, ;
,,
,
,
i l i i i
l i l I i i i
l i l l t
l
, t
, i i
l i i i i t
!
61l710:2l n ini1 n ioin C
i lt l8 5 6,1l7i2i6l D i0 i3 linin C
i l1 l
^
^
i c
t i
i liil l
l
'
'
i i i i i
i e i i i
i i li,i liiI c
i,
i i i
i i i i i
I,,1
!,,1
=
,,
,,
,
i,
,,
,
a i
5 6,1l70i31 0i017 Oi9i5 C
i lr l
i s
i 5 7til7 0 71 0i017 Oi6i6 'r i liil
^
^
i lt i l i i i i i lI l
'
i i i i i
i liiI c
IiiI c
i i i i i
i i i i i
!
I,,I I,,l
-
,,
, i
,,
,,
,
,
5 6 ll7i0i4 l Oi0,2 licio c i
O 0 6 0,7 3'C liil 5 7:1l7,09l i i i
i li i l
^
^
e i
i i i l i i
l i i i l i i
l i l i i i i
i i l i i i i
i f oCRCLE SEQUENCE IF
"
l 1 l l l
l { l l
-
l i
i l
l r
"
l l l l l l l l t[ulal3
.h,) 4 l5 tm
'
sa to va to e
sa n
- ,.
.e. _s,,
..
.,
,..
-
-,
-
Sheet 2 of 2 Nac FORMES U.S. NUCLEAR LEGULATORY COMMISSION PRINCIU4 tNSPCCTORINeae test irst arW W.,se ares i t 1418
.
,E uC cus, -
INSPECTOR'S REPORT
,, y,, y,
Office of Inspection and Enforcement iN S, tCTOL S LICENSEE / VENDOR TR ANS ACTION DOCnET NO t8 attss OR LICENSE REPORT NEXT INSPEC DATE NO. tsv PRODUCTitt3 dersi g
3g 1 -tNSERT
-
M - MODIFY
"
A n n n
o d
2
1 n
^
~
~
-
-
-
-
It 0 - DELETE
-
C'
M - REPLACE D
atQ O.& c,
- t' p., e"c r :. $ : > o -
_
1s sg
F E~:OD OF INVE STIGATION dNS PECTION INSPECTION PERFORMED 8 f ORGANi2ATON C.CCE OF REGONIMO CONDUCT.
F*OM TO 1 - REGION AL OFFICE STAFF OTHER
'
'
m-Wees4 Maroower R ovrm kw coce )
MO DAY VM.
MO DAY VR 2 - RESIDENT INSPECTOR JEGON
.
O'* SON
.
BAANCH l
l l
l l
l 3 - PERFORMANCE APPRAISAL TEAM l
f
25 28 -
. 31
<**: t Z.
A > ? 32 C
l
l
'
e
-
REGIONAL ACTION TYPE OF ACTiviTV CONDUCTED (Check one boa orwyl
"
02 - SAFETY
_
06 - MGMT. VISIT to - PLANT SEC,
_
14 - INQUIRV
_
-
1 - N2C FORM 591
-
03 - INCIDENT 07 - SPECIAL 11 - INVENT.VER 15 - INVESTIGATION 2 - F.EGION AL OFFICE LETTER 04 - ENFORCEMENT
-
-
-
08 - VENDOR 12 - SHIPMENT. EXPORT 05 - MGMT. AUDIT 09 - MAT. ACCT.
13. IMPORT
- **
'li'
- M 37'3
'
.N5PEC TicN iN vES T> GAT.GN F'NCnNG5
' Charm one nos oneva TOTAL NUMBER ENFORCEMENT CONFERENCE REPORT CONTA6N 2 790 LETTER OF REPO 4T TR ANSMITTAL DATE OF VsouTONS AND HELD INFORMAT10N A
e C
D DEviADONS NRC FORM 591 REPCRTSENT
,
OR REG TO HQ FOR
_
LETTER IS 5UED ACTION l 9 C
D Al8 Cl0 3 - DEVIATION A
A
C D
MO.
DAv VR MO.
day vn
,
4 - VIOLATION & DEVIATION l
l l
1 - VES 1 - VES l
l l
l l
l
,
,
,
,
- 39
-
.m 4441)
.'s-
-]-
42'
44
50
MODULE INFORMAT'ON MODULE >NFOaM avion
'$
MODULE NUM8ER INSP dg 9 MODULE REQ. FOLLOWUP n[g MODULE NUMBER INSP yg 9 VODULE REQ FOLLOWUP E3 5]E35 ie a
55 3 3e r
r
.
h!Sc IEr=
- !
!s s
!!
. s h!!c 5 5 : s-!!
!s e
i
s e s i !s Ei i;5 yis5 9iE? _!%
8I ie I i
.,
s!% 8I i s B QiEs 2 s E 3Ni3 8i s
I 2 5
edI s naz r8e:
I s5
- !
c 3 I
Ea
I a_a:=
r8E
=c sv is
a i
5 7 il l7 1,1 l
^
Oi0i9 li0,0 C
i liil8 i
i liil i i i e i ll t l
^
Iiil
liil
i i i i i
i i i i i
liil c
IiiI c
r i i,
i i i i i i
liil e
ii,I o
i,
i,
i e i i i
,
liiI^
liile liiI^
Iiil
-
,
i i,
, i
,
,
i i i i,
i liil
-
Iiil e
i,
,,
i i,
i,
,
li,I liiI c
c ii i i i
i i i,
i l,,I o
I,,I o
i,
,,
,
,,
,,
,
liiI^
liiie liiI^
liiI
.
i i
ii i,
i i
i i i i i i
liil
$
Iiil
-
ii
,,
i i i i t i
l Ii,i liiI c
c ii
, i i
i i i i i
I I,,I iiil o
,,
,,
i
> i i i i
liil^
liile liiI^
I liil
- .
,
i ii i i i
i i
, i i,
i l,,l l,,
a l
a
,,
,,
,
,,
,,
,
iI
!
'
1 i i i i
,
i i i i t
I i O CIRCLE SEQLENCE iF I
l C
=
VIOLATION OR CEVIAh0N l l l l
[
l l l l l
l l l l
l l f t,iup p e
e n, m
e n
ee.
o,, c.n n
_m.,
..
. --