IR 05000482/1990015
| ML20042G492 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/07/1990 |
| From: | Kelley D, Seidle W, Singh A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20042G488 | List: |
| References | |
| 50-482-90-15, NUDOCS 9005140293 | |
| Download: ML20042G492 (12) | |
Text
..w-l
- ,
- ., :
.,
,
'
-
,
f APPENDIX ~
,
U.S. NUCLEAR REGULATORY COMMISSION
,
REGION IV
'
NRC Inspection Report:
50-482/90-15
. Operating License: HPF-42-Docket: 50-482.
'
,
-Licensee: -Wolf Creek Huclear Operating Corporation (WCN00);
]a i.-
P.O. Box-411 Burlington, Kansas. 66839 GeneratingStation(WCGS)
.i Facility Name: Wolf C::2.
Inspection At: WCGS, Cof1ey County, Burlington, Kansas Inspection Conducted: April 23-27, 1990'
Inspectors:
-
'E 5/7/W'
,
A. Singh, ea(Jor Inspector, Tesl.. Programs Date
<'
Section, Division of Reactor Safety
<
p
_
//h6
!
- D. L. Kelley~,. React fin (pPJtor, Test Programs Da t'e ' '
Section, Division of Rerctor Safety I-Accompanied By:
W. C.'Seidle. Chief, Test Programs Section
' Division' of Reactor Safety (April' 26-27)
'
ij C
' Approved:
._
- /p/</o
'
W. C. Seidlt/, Chief, Test Programs Section Date Division of Reactor Safety Inspect, ion Summary o
Inspection Conducted April 23-27, 1990 (Report 50-482/90-15)
,
Areas Inspected: Rcutine, announced inspection of the verification of isolationcomponentexemptions(VOICE).
p Results: Within the area inspected, no violations or deviations were identified. The licensee has a strong program in the area of containment integrated leak rate testing (CILRT) and local leak rate testing (LLRT). A 100' percent visual inspection of containment penetrations was performed by the 90031 Y O ' 93 96e.q a
MCO yht J
Y
.
roc
'.;
s
.
.
-
.
.
^
,
>
-r
- s
,
.
.
,
- r.
.i
'
-2-ji
.
~
i
,
>
,
m
.
- Linspectors,inside and outside the containment building. The inspectors did not
'
.j g Lobserve ani significant discrepancies. The inspectors did note that-the; spare
.
,e
- penetrations were not labeled and six valves did not have tags.. The licensee
,
.
--took prompt-corrective 1 actions to label the spare penetrations and repla.'e' the
,
ft missing tags. The: areas ~ inspected were clean and free of trash indicating
.
'
<
that, although.the plant was in a refueling outage, the licensee had a.well k
fimplemented and vigorous housekeeping effort.
s
.i
-
'l r
i
.
I i
l'
i.
?
'.
l l
.
.
.
,
t
'.
.
. - - - -..
- - -
- -.. - -. -
- - - - -
.
'
n;
,
- .
g.
.,
w
,
'
b-3-
,
,
DETAILS
__
m l'.
. PERSONS' CONTACTED
,
.r
,
,
WCNOC-
,
. J. A. Bailey, Vice_ President, huclear.0perations
- R.:S. Benedict, Manager Quality Control (00) -
.
- *B. Bergstrom, Supervisor, Maintenance and Modification Services Group
.R.~~ Li Birk, Trainer
- G. D. Boyer, Plant Manager
- H. K. Cherneff, Supervisor, Licensing
.
,
.
- A.:B. Clason,: Manager, Engineering Supervisor
,
' ' M. E. Dungloz, Manager, Nuclear Power Engineering System-m t '
- R. D. Flannigan, Manager, Nuclear-Services y;
,
',
- C. W.! Fowler, Manager, Instrutrentation and Control
-
.-K. Harvey, QC Supervisor 5.
,
' *R." W. Holloway, Manager, Modification m '
,
, D. Hopper, Licensing. Specialist
'
- D. Jacobs, Supervisor, Engineering a
'*W. M. Landsay, Manager, Quality Assurance (QA)
-
-
- R. Lagsdon, Manager, Chemistry
'R.-Lee, Licensing Engineer 1.
-*R.iK.-Lewis, Supervisor,'Results Engineering
_ 0. L. Maynard,- Manager, Regulatory Services
-
.
t
- M. H. Mesehee, Supervisor, Compliance Engineering
- D. G. Moseby, Supervisor, Operations
- C. E. Parry, Director, QA B..A.5Pae,--Results Engineer
- J.-M._ Pippin, Manager, Nuclear Plant Engineering
- F. T. Rhodes, Vice President, Engineering and Technical Services
.
- H. L. Stubby, Supervisor, Technical Training'
- J. Weeks,. Manager, Operations -
- S. Wideman, Sr., Licensing Specialist
- M. G.LWilliams, Manager; Plant Support
- B. D. Withers, President, WCNOC
- J.- A.:Zell, Manager, Training'
~NRC
+ '
H. F. Bundy, Reactor Inspector, Region IV
- M. E. Skow, Senior Resident'. Inspector
'
,
- The inspectors also interviewed other licensee employees during the inspection.
-* Denotes those attending the exit meeting conducted on April 27,.1990.
i q.
-
r6, q
'
3 ;l [a
'
c
G
.i
! -
j V
2.
VERIFICATION OF CONTAINMENT INTEGRITY (61715)
!
The purposes of the inspection were to identify all containment penetrations and their associated isolating components and to verify that they were identified on P&lDs or other drawings; to determine which components have been
+
excluded from Type A, B,~ or C leak rate testing programs; and to verify that
'
the containment' penetrations and associated isolating components, excluded from U
the Type A, B, or C-leak rate testing programs, meet either the criteria for
,
waiver approval by the NRC Office of Nuclear Reactor Regulation (NRR)given test exemption, as set forth in Appendix J to 10 CFR Part 50 or have been
-
J A..
g
.
iThe inspectors performed a 100 percent walkdown, which involved 109 mechanica_1
- and 81 electrical containment penetrations, and 384 isolation valves associated
,
with these penetrations. This inspection.was performed inside and outside the
.
containment building, and, wherever possible, the inspectors traced associated system piping coming through an identified penetration back to its designated g
"
containment isolating component on either side of the containment building wall. The inspectors listed all of the penetrations and isolating components
. identified and compared this list with the associated controlled P&lDs
.;
identified in the Attachment.
It was noted during the containment walkdown
!
that'the 25 spare-~ penetrations were not labeled.- The inspectors also observed that six isolation valves-were without tags. The licensee took prompt
corrective action to correct the problem concerning the missing tags and
labels.
In addition to the missing valve tags,-the inspectors noted that
.. component tags subject to elevated temperatures were deformed with some being Ldifficult to read. The inspectors questioned-the licensee's choice of plastic-for permanent component tags. The remaining-penetrations and associated isolation valves were appropriately labeled and tagged.
The inspectors noted that the plant areas inspected were clean and free of trash indicating a well implemented and vigorous housekeeping effort. The
inspectors compared P&lDs with Procedures STS PE-017 and 18. The review did
not identify any discrepancies between the P&lDs and the proce@res. The
-
inspectors also noted that the P&lDs and the isometric drawings were being A
updated regularly.
.
.
The licensee stated that they do not have any exemptions from the Type A, B, or j
C tests.
-
'
No violations or deviations were identified in this program area.
3.
CONTAINMENT LOCAL LEAK RATE TESTING (61720)
The purpose of this inspection was to verify that primary containment local
. leak. rate tests (LLRT), as required by the Wolf Creek Generat;ng Station (WCGS)
!
Technical Specifications (TS), were performed to ensure that leakage through
,
testable containment penetrations and isolation valves would not exceed the allowable leakage specified. This review included records, procedures, and g
l independent calculations associated with the LLRT Type C tests.
p
.
..
_
a-
.
.
.
-
.
.
,
,
F-5-During the inspection, the inspectors reviewed the primary containment LLRT procedure STS pE 017, Revision 7, dated September 28, 1988. The procedure was
complete and satisfactorily stated the ecceptance criteria for each penetration and the associated containnent isolation valve (CIV). Test procedure instructions were concise and previded for independent verification of test results and for system restoration. The inspectors reviewed records of LLRTs conducted during 1988.
In conducting this review, the inspectors verified that
.
corrective actions were taken on excessive leakage components and that I
appropriate retests were conducted on penetrations and CIVs. The cumulative data for containnent testable penetrations and CIVs were reviewed to verify that the containment local leak rate did not exceed the acceptance criteria.
Yhe LLRT test results were well within the acceptance criteria required by TS.
The inspectors' concluded that the licensee had a strong progrtm in the area of LLRT.
No violations or deviations were identified in the review of this prog'um area.
r
EXIT INTERVIEW
An exit meeting was held on April 27, 1990, with personnel identified in l
paragraph 1 of this report. At the crit interview, the inspectors summarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the information provided to, or reviewed by, the inspectors.
e l
.
/
-
_..
- _ _ _ _ _ _ _.. _ _ _ _ _ _ _
i
.
,.
.-
,
.
ATTACHMEtiT A.
@,TAltlMEt!TPENETRATIONINDEXANDDRAWINGS Pen.
Type of
&
Test Description P&ID P-1 A
Main Steam Line M02-AB01 P-2 A
Main Steam Line M02 AB01 P-3 A
Main Steam Line M02-AB01 P-4 A
Main Steam Line M02-AB01 P-5 A
Main and Aux. Feedwater to Generator M02-AE02 P-6 A
Itain and Aux. Feedwater to Generator M02-AE02 P-7 A
Main and Aux. Feodwater to Generator M02-AE02 P-8 A
Main and Aux. Feedwater to Generator M02-AE02 P-9 A
Steam Generator Blowdown M02-BM01 P-10 A
Steam Generator Blowdown t102-BM01 P-11 A
Steam Generator Blowdown M02-BM01 P 12 A
Steam Generator Blowdown 1102-BM01 P-13 A
CTMT Spray Suction from CTMT Sumps tiO2-Ell 01 P-14 CA RHR Pump Suction from CTMT Sumps M02-EJ01 P-15 CA RHR Pump Suction from CTMT Sumps M02-EJ01 P-16 A
CTMT Spray Suction from CTMT Sumps M02-EN01 P-17 B
Fuel Transfer Tube M02-EC01/EC02 P-18 Spare P-19 Spare P-20 Spare P-21 A
RHR Pump Disch to RCS Hot Leg for Recirc 1102-EJ01 P-22 C
Reactor Coolant Pump B Seal Water Supply M02-BB03/B001 P-23 C
Chemical Volume Control System M02-BG01/BG04 Letdown Line M02-BG02 P-24 C
Reactor Coolant Pump Seal Water M02-BG03 Return M02-BG01 P-25 C
ReactorMakeUpWaterSupply M02-BL01 P-26 C
Reactor Coolant Orain Tan., Discharge M02-HB01 P-27 A
RHR Pump Discharge to RCS Cold Leg M02-EJ01 P-28 C
Essential Service Water Supply to M02-EF02 CTMT Coolers M02-GH01 P-29 C
Essential Service Water Return from M02-EF02 CTMT Coolers P-30 C
Instrument Air Supply & H M02-GN01
Control Makeup Air M02-KA01 P-31 Spare P-32 C
Containment Sump Pump Discharge Line M02-LF09 P-33 Spare P-34 B
CTMT Test Line - ILRT Pressurization 802-GP01 P-35 Spare P-36 Spare P-37 Spare P-38 Spare l
- -.--...
.
.
,.
-2-i P-39 C
Reactor Coolant Pump C Seal Water M02-BB03 Supply M02-BG01 P-40 C
Reactor Coolant Pump D Seal Water M02-BB03 Supply P-41 C
Reactor Coolant Pump A Seal Water M02-BB03 Supply M03-BG01
!
P-42 Spare P-43 C
Auxiliary Steam Decontamination M02-HD01 P-44-C Reactor Coolant Drain Tank Vent /Hp Supply M02-HB01 P-45 C
Accumulator H Supply M02-EP01 p
P-46 Spare P-47 Spare P-48 A
S1 Pump Hot Leg Recirculation M02-EM01
,
P-49 A
S1 Pump Disch to Cold Leg M02-EtiOI P 50 Spare P-51
Integrated Leakage Rate Test Pressure Sensing M12-GP01 P-52 A
RHR Pump Suction from RCS Hot Leg M12-E001 P-53 C
Refueling Pool Cooling and Cleanup Supply M02-ECO2-P-54 C
Refueling Pool Cooling and Cleanup Return M02-EC02 P-55 C
Refueling Pool Skimmer Line M02-EC01/EC02 P-56 AC Hydrogen Sample M12-GS01 P-57 AC Liquid Sample and flush Water Return to RC Drain Tank M12-SJ04 P-58 C
Accumulator fill Line, HPC1 M12-EM01 P-59 RYLIS Sample Line RX Coolant System P-60 Spare P-61 Spare P-62 C
Pressurizer Relief Tank Hitrogen Supply M12-BB02 P-63 C
Service Air Supply M02-KA02 P-64 AC RC Loops & Pressurizer Liquid Sample M12-$004 P-65 C
CTliT Hydrogen Purge M12-GS01 P-66 A
Spray Pump Discharge to Containment til2-EN01 P-67 C
fire Protection M12-KCO2 P-68 Spare P-69 C
Pressurizer Vapor Sample Line M12-SJ01 P-70 Spare P-71 C
Essential Service Water Supply to CTMT Coolers M12-Ef02 P-72 Spare P-73 C
Essential Service Water Return to CTiiT Coolers M02-Ef02 P-74 C
Component Cooling Water Supply to RCPs M02-EC03 P-75 C
Component Cooling Water Return to RCPs tiO2-EG03
..._ _ _.:
..
,.
.
,
.
-3-
,
P-76 C
Component Cooling Water from RCP Thermal Barrier M02-EG03 P-77 Spare P-78 C
Steam Generator Drain Line M12-BP01 P-79 A
RilR Purp Suction From RCS Hot leg M12-EJM P-80 C
Chemical Volone and Control Charging M12-BG01/'4G03
.
P-81 Spare P-82 A
RHR Pump Disch to RCS Cold Legs M02-EJ01 P-83 A
Steam Generator D Sample Line M12-BM01 P-84 A
Steam Generator A Sempie Line M12-BH01 P-85 A
Steam Generator B Sample Line M12-CM01 m
P-86 A
Steam Generator C Sampie Line M12-CH01 P-87 A
S1 Pump Hot Leg Reciretnation 1112-EM01 P-88 A
Boron Injection Tank N s:h Line M12-EM02
P-89 A
Spray Pump Discharge 'tc. OTMT M12-EN01 P-90 Spare P-91 A
RVLIS Sample Line Rx b raant System P-92 C
Emergency Core Coohnt Spray Test Line Connection M12-EM01/0N01 P 93 C
RC Loop and Pressurwer Liquid Sample M12-SJ04 P-94 Spare P-95 C
Accumulator Sample t u e M12-SJ01 P-96 Spore-P-97 A;
H, Control System Sam;1e Return M12-GS01 P-98 C
Breathing Air Supp7y M12-K001 P-99 AC Ho Control System St.r;ae Line/ Pressure 56nsing M12-GN02 P-100 Spare P-101 AC H,, Control System Serre Line/ Pressure Shnsing M12-G501 P-102 Spare P-103 A
CTM1 Pressure Sensing M02-GN01 P-104 A
CTMT Pressure Sensing M02-GN01 V160 C
CTMT Purge System M12-GT01 V161 C
CTMT Purge System 1112-GT01 L-1 B
Personnel Lock L-2 B
Equipment Hatch L-3 B
Emergency Personnel Lock E 207 B
Electrical Penetration E-035 MediumVoltage(18")
E 208 B
Electrical Penetration E-035 11edium Voltage (18"1 E 264 B
Electrical Penetration E-035 MediumVoltage(18")
E 265 B
Electrical Penetration E-035 Medium Voltage (18")
E 226 B
High Current Density (12")
E-035 E 219 B
High Current Density (12")
E-035
n;
-
,s-y e, e t.
4-
l E 208 B
High Current Density 12" E-035
E 210 B
High current Density 12" E-035
'
'
E 274 B
High Current Density 12" E-035 E 218 b
Power and Control 12" E-035
E 269 B
Power and Control 12" E-035
'
E 234 B
Power and Control 12" E-035 E 225 B
Power and Control 12
E-035
.
E 283 B
Power and Control 12" E-035
E 284 B
Power and Control 12" E-035 E 276 B
Power and Control 12" E-035 E 275 B
Power and Control 12" E-035 E 233 B
Power and Control 12" E-035 E 277 B
Power and Control 12" E-035 E 224 B
Power and Control 12" E-035
.
E 222 B
Power and Control 12" E-035 E 223 B
Power and Control 12" E-035 E 240 B
Power and Control 12" E-035 E 270 B
Power and Control 12" E-035 E 280 B
CRDHechanism(12" E-035
'
E 271 B
CRD Mechanism (12" E-035 E 272 B
CRD liechenism 12" E-035 E 290 B
CR0 liechanism 12" E-035 E 287 B
CRD Mechanism 12" E-035-E 2B5 B
Power and Control 12")
E-035 E 291 B
Sener61 Instrumentation (12")
E-035 E 250 B
Ex-Core Neutron Detector 12*
E-035 E 25B B
Ex-Core Neutron Detector 12" E-035 E 295-B Ex-Core !!cutron Detector 12" E-035
!
E 288 B
Ex-Core Neutron Detector 12" E-035
E 292 B
GeneralInstrumentation(12")
E-035 E 293 B
GeneralInstrumentation(12")
E-035 E 289 B
CRD Mechan'sm (12")
E-035
'
E 252 B
General Instrumentation 12" E-035 E 255 B
General Instrumentation 12" E-035 E 253 B
Cencral Instrumentation 12" E-035 E 294 B
General Instrumentation 12" E-035-E 287 B
General Instrumentation' 12" E-035 E 243 B
General Instrumentation 12" E-035 E 279 B
General Instrumentation 12" E-035 E 249 B
General Instrumentation 12" E-035 E 254 B
General Instrunentat on 12" E-035 E 267 D
Power & Control (12")
E-035 E-282 B
Power & Control (12")
E-035 E-215 B
Encapsulated Valve E-035
"
E-216 B
Encapsulated Yalve E-035
"
E-217 B
Encapsulated Valve E-035
>
E-296 B
Encapsulated Valve E-035
,'
E-297 B
Encapsulated Valve E-035
"
E-298 B
Encapsulated Valve E-035
"
,
L
y
-
- .
.
'
'.
,
,.
-
,
.
.
5-
!.
j..
h E-256 B
CTitT pressure Sensing N02-GN01
-
i E-206 B
Ground
'
L E-209 B
Spare
!.
E-211 B
Spare E-212 B
Spare
_
E-213 B
Spare
'
E 220 B
Spare r'
E-221 B
Spare L
E-227 B
Spare E-228 B.
Spare i
!.
E-235 B
Spare i
E-236 B
Spare L.
E-237 B
Spare i
E-238 B
Spare E-239 B
Spare t
E-241 B
Spare E-242
.B Spare E-251 B
Spare E-257 B
Spare E-261 B
Spare E-262 B
Spare
'
E-263 B
Spare
E-266 B
Spare
'
E-270 B_
Spare E-273 B
Spare E-286 B
Spare
,
B.
pROCEDURg Procedure No.
Title Date s
,
STS pE-017 Local Leak Rate Test 9/25/88 STS pE-01B Containinent Integrated Leak Rate Test 12/11/B9-
.
C.
OTHER D_0CUMENTS
,
Wolf Creek Final Safety Analysis Report, Section 6.2.6,
" Containment Leakage Testing"
,
Wolf Creek Safety Evaluation Report, Section 6.2.3,
"
!
" Containment Isolation System," and Section 6.2.5,
Containment Leakage Testing Program"
-'D COMPLETED LOCAL LEAK RATE TESTS
.
..,
Test Penetration CKL PE-014 P-14
m b
..
,
I i
t g
- 4 ;, <
- -. 4 -
,
.
-s-
$'
CKL PE-015 P-15 CKL PE-017 P-17 CKL PE-022 P-22, P-39, P-40, P-41 CKL PE-023 P-23 CKL PE-024 P-24 CKL PE-025 P-24 CKL PE-026-P-26 CKL PE-032 P-32 i
CKL PE-034
. P-34 CKL PE-043 P-43 CKL PE-044 P-44.
CKL PE-045 P-45 CKL PE-051 P-51 CKL PE-053 P-53 CKL PE-054 P-54
CKL PE-055 P-55 CKL.PE-056 P 56 CKL PE-L67 P-57
.CKL PE-058 P-58 CKL PE-062 P-62 CKL PE-063 P-63-CKL PE-064 P-64 CKL PE-065 P-65 CKL PE-067 P-067 CKL PE-069 P-069 CKL PE-071 P-71, -73 CKL PE-074 P-74 CKL PE-075 P-75 CKL PE-076 P-76 CKL PE-078 P-78 CKL PE-080 P-80 CKL PE-092 P-92 CKL PE-093 P-93 CKL PE-095 P-95 CKL PE-097-P-97 CKL PE-098 P-98 CKL PE-099 P-99 CKL PE-101 P-101
.CKL PE-002 L-2(EquipmentHatch)-
CKL PE-160 Y-160 CKL PE-161 V-161 STS PE-020 L-3 DoorSeals)
STS PE-014 L-3 Airlock)
STS PE-013 L-1 Air Lock)
STS PE-032 L-1 DoorHandwheelShaftSeal)
STS PE-015 18-inch Purge Valve CKL PE-163 South Bank of Electrical Penetrations
{
i
-1
-,
lp
.
,
-;. * * *
. *
,
CKL PE-164 North Bank of tiectrical Penetrations NOTE: CKL's (check 115,ts) are used during perfonnence of LLRT Procedure STS-PE-017.
-
,
s
!
<
$
.!