IR 05000382/1989035
| ML19325E936 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/31/1989 |
| From: | Clay Johnson, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19325E934 | List: |
| References | |
| 50-382-89-35, NUDOCS 8911130051 | |
| Download: ML19325E936 (9) | |
Text
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' U.S. NUCLEAR REGULATORY COMM15510N '
REGION IV
- y r19 NRCInshection. Report: 60-382/89-35 Operating License: NPF-38 , , lL , . q Docket: 50-382 . . Licensee: 'LouisianaPower&LightCompany(LPAL) 317 Baronne Street , 'New Orleans. Louisiana 70160
' ' - a l Facility Name: Waterford Steam Electric Station. Unit 3 (Waterford 3) ?; + - , Inspection At: Taft. Louisiana f: Inspection Conducted: October 16-20, 1989- ' , %
Inspector: _ /d/'f//B1 ~ ) , C. E. Johnson. Reactor Inspector. Plant Dat( < i Systems:Section. Division of. Reactor Safety L - , , , i ' , sApproved:. \\ Md ' /o[y/Ih T. F. Stetka. Chief. Plant Systems Section Datf
, Division of Reactor Safety l ,
- ' , Inspection Sununary - . . , i ._ Inspection Londucted October 16-20, 1989 (Report 50-382/89-35) j . , l heasInspected: Routine, unannounced inspection of piping suppnrt and '
restraint system testing, and sefety-related protective coatings inside
' H e containment.
'; , Results: One violation was identified (paragraph Pb). involving a failure of , ,, operations personnel to comply with radiological warning signs. An auxiliary j ' ! - operator violated a radiation work pemit requirement which required a full set t , of anticontamination protective clothing while climbing into contaminated j + areas. On'May 26, 1989, a similar incident involving an auxiliary operator in l i i n-a contaminated area was observed. This incident is documented in NRC
l.o inspection Report 50-382/89-12.
-] It. appears that more management involvement is needed in this area especially l '
l since there was similar violation identified this year.
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. +... ,t-s: Review of the?l'icensee's' program for piping supports and restraint systems and
- the program.for safety-related protective coatings, indicates that management j & . > h,' attention 1s adequate in these areas.
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, - V } . , ' , RETAILS , < L s ~ { 1.; Persons Contacted LPAL " '
s s R. P. Barkhurst, Vice President, Nuclear Operations
- *J. R. McGaha, Plant Manager, Nuclear
- P. V. Prasankumar Assistant Plant Manager, Technical Support
[% - *D. F. Packer.. Assistant Plant Manager, Operations and Maintenance A. S. Lockhart, Quality Assurance Manager L
- D. E. Baker, Manager of Nuclear Operations Support and Assessments
- W. T. La$onte.. Radiation Protection Superintendent
"
- G. M. Davis, Manager of Events. Analysis Reporting & Responses
- L. W. Laughlin, Onsite Licensing Coordinator
- G.. Robin,.ISI Coordinator 1 -
- J.,J. Zabritski, Operations QA manager
> ~
- T. H. Smith, Plant Engineering Superintendent
- W. R. Brian, System Engineering Supervisor
- S. Ramzy, Assistant Radiation Protection Supervisor
- L. L. Bass, N0EC Training'
- P.'N. Backes, Programs. Engineering Supervisor
. *J. E. Howard, N0EC '
- L. R. Simon, Radwaste' Engineer
' W. R. Brian, Systems Enginecring Supervisor G.'F. Koehler, Operations QA Supervisor J. Schlesinger, Systems Engineer C. Forpahl, BOP, ISI Coordinator
M. E. Smith, ISI Coordinator .. , J. Burke, Lead Senior Engineer, Civil . j Wyle Laboratories Scientific Services (Wyle) ' T. Reid. L-II Technician E. Breach, L-I Technician l ' C. Goins, L-I Technician ' NRC p nc' W. F. Smith, Senior Resident Inspector
- T. R.'Staker, Resident Inspector l
F. Hebdon, NRR i '.
- W. M. McNeill, Reactor. Inspector
, . , !
- R. E. Baer, Health Physicist
'
- Denotes those individuals attending the exit interview.
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V 2.
Testing of Piping Support and Restraint Systems (70370) l The purpose,of this inspection was to detemine if the licensee has ! P-established an approved program and adequate procedures pertaining to the ! exemination and testing of piping supports and restraint systems and
whether they are in compliance with Technical Specifications. (TS) and !( commitments.
$a.
Procedure Review g , I
- The iequirements for the hydraulic and mechanical snubbers are r
- covered by TS Sections' 3.7.8. and 4.7.8.
Section 3.7.8 gives the Limiting Conditions for Operation (LCOs) for snubbers and Section 4.7.8 j , ,'; -. lists the surveillance ~ requirements for the perfcmance of snubber
.
- inspections. The requirements for the rigid and component supports, d
, Classes 1, 2, and 3. are covered by the 10-year ISI program.
' 'Theinspectorreviewedprocedurespertaining(to.mechanicalandISI) procedures hydraulic snubbers and Inservice Inspection rigid and component < supports. Procedures reviewed are listed in- , Attachment 1.
, Procedures reviewed by the inspector appear.to be adequate.
It was ,s ' noted by the inspector that the licensee has an ongoing sn.ubber - , reduction program in place. The licensee has requested'and received NRC approval to use ASME Code Case N-411-1 to optimize the number of , seismic restraints (snubbers) in v'arious piping systems. For the <> . ' 'ISI program covering pipe supports, the licensee has been granted > r relief by.the NRC to reduce the number of supports requiring inspection (approximately 160 rupports) which are inaccessible for examination
. due to permanently installed fire seals and permanent nonremovable ' " insulation.
o No violations or dev1ations were' identified.
, ' b.- Field Observation Surveillance Inspections , The inspector observed the examination of five supports under the ISI program by US Testing personnel. The ins 9ector also independently - examinedfourteenpipesupportsincludedintheISIprogramand sixteen snubbers. Attributes that were selected for observation in L the visual examination are listed as follows: -s Deterioration, corrosion, physical damage, or deformations were
not evident; ' All required bolts, locking devices, nuts, and washers were
. installed; , 4.
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. } ~ - . . j Extension rods ' support plates, and connecting joints were not
[ , bent, defonned, or loose; - , j Snubber settings; .!
r S,i . Pipes, supports,~or other associated equipment or components
' , .. , were'not restricted-or in contact with other surfaces as a- , h, t result of thennal expansion;'
, c e < L Springs in hangers were not obstructed'by foreign material;
' ' Indicators or spring hangers show either " cold" or " hot"
position, consistent.with the present plant condition; and Threaded connections were secured by. locknuts, fasteners, and.
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The supports examined are listed in Attachment 2 of this report. V ' , Overall,'the pipe supports examined were acceptable, and the US ,~ f Testing personnel adhored to the licensee's procedures.
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There was one support identified by the inspector which appeared as if the clamps around the piping were misaligned. Support No. SIRR-887 ' , . c was located in a'high radiation area. The ISI coordinator imediately i initiated a Condition, Identification (CI) report (No. 265954) on this , support. The ' inspector considered this deficiency to be an isolated l' case in an otherwise acceptable program.
' . '. ' . During the field examination, conducted on October 18, at about 11 a.m., the inspector observed a licensee. individual in Safety ' ' . Injection Pump Room B climbing on pipes checking tags on valves.
This individual was.not wearing the full anticontamination protective ' .; clothing required by the Radiation Work Permit (RWP).. Failure to adhere to the requirements,0f-an RWP is contrary to the requirements
' of Technical Specifications- (TS) 6.11.1.
This appears to be a recurrence of a similar violation identified on M May 26', 1989, in NRC Inspection Report 50-382/89-12.
It appears e
that the licensee's corrective action was inadequate.
..g Violation (382/8935-01): Failure to adhere to the requirements of radiation protection procedures involving entry into contaminated areas.
. L ,m Functional Testing 1, The inspector witnessed functional testing of three mechanical , snubbers performed by Wyle technicians. Observations indicated that - t f
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h ' ' . > ~. the supports tested met initial running drag, acceleration, and final > L , running drag acceptance criteria. No deficiencies were observed.
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, , - < ' ,~The supports observed,are listed in Attachment 2.
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Records Review
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, . ,* The inspector reviewed records of all supports examined during the ,, - , field examination.. functional test data by Wyle, calibration records
of the functional test equipment, visual examination records performed by US Testing on ISI supports, and surveillances of the
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! snubber program conducted during refueling outages (RF) I and 2.
.
Records reviewed indicated the following: , .
Functional' test of snubbers were within the established - , acceptance' criteria.
i _, r Identified deficiencies were noted and documented on the visual
- examination record for ISI support and snubbers.
Sample size was expanded and additional supports were selected
4 as required by TS when a functional test failure occurred on
snubbers.
j . - ' ' Surve111ances are perfonned as. required by TS., L
Functional test equipment was in calibration.
.y , No violations or deviations were identified.
d.
Summary-In conclusion, the inspector determined that adequate programs and [ procedures pertaining to'the examination and testing of piping- ,, supports and restraint systems have'been established and are in compliance with the TS and licensee commitments.
It is apparent that
licensee management involvement is evident and is considered to be a - strength in this prcgram.
{ 3.
Protective Coatings (In Containment) (93702) During this inspection, the inspector examined protective coating status inside containment and reviewed the licensee's protective coatings , program.
y During a plant tour inside containment the inspector noted that protective coatings were peeling off the steel liner in various arees.
It appeared that the-top. coat of protective coatings was peeling from the prime coat.
~ The prime coat, however, was still intact on the steel liner.
No indications of rust or corrosion were evident.
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5-7-c .x - " r 3. Further investigation indicated'that the~ licensee had established and' , . implemented a containment coatings surveillance program as~ committed to ., the NRC by letter dated February 27. 1985.
,
-The' inspector reviewed two procedures and examined the surveillance
L records documented during" refueling outages (RF)' I and+ 2.
Repairs.to,the peeling coatings have begun'and will be completed during RF-3 'and future , outages.
s Procedures, reviewed are listed in Attachment'1.
i In ~ summary, the inspector determined that the surveillance and repair program for protective coatings that'the licensee has committed to was being properly implemented.
' ~ ' ' No' violations or deviations were identified.
, ' ' ' 4.- Exit Interview , n [ The inspector net'with Mr. J. R. McGaha and other members of the licensee's staff at~the end of.the inspection. At this meeting, the inspector summarized the scope of the. inspections and the findings. The licensee ol ' did not identify as proprietary any of the'information provided to, or reviewed by, the inspector.
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,c.".- r s , ) 'p,'e ( r- - '3" ATTACHMENT 1 - ) l- < . [- PIPE SUPPORT PROCEDURES
- , s PE-5-014. " Snubber Sampling and Functional Testing," Revision 5 j
PE-5-011. " Mechanical Snubber Visual Irspection," Revision 5 ! ' " , PE-5-012. " Hydraulic Snubber Visual Inspection," Revision 3 [ !
, l ' MM-7-011. " Mechanical Snubber Test " Revision 3 i e':
,
' OAP-384, " Visual Examination (VT-1)," Revision 0 '~
OAP-386, " Visual Examination (VT-3)," Revision 0.
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, , QAP-387, " Visual Examination (VT-4)," Revision 0 l
< - , PROTECTIVE C0ATINGS PROCEDURES , r . (. < ' ' N0El-303 " Conducting Engineering Inspection _of Reactor Containment > Building Protective Coatings," Revision 0, dated August 10, 1987 , MM-6-100, " Maintenance Painting," Revision 3, dated January 2,1987
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. ATTACHMENT 2 - , , ' " ,., ,. ' >
- , h '" ' SUPPORTS VISUALLY EXAMINED '
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' A Snubbers-ISI Supports
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. SIRR-0894 * '
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i SISR-1055
'SISR-1188" SIRR-0488 *- ' '. , 'SIRR-0490 * SISR-1136 , 'FWSR-11 SIRR-3001 * ' FWSR-23 SIRR-0373.* - FWSR-14 SISR-0215 > FWSR-14A SISR-0773 ',' ~ SIRR-0887 . l SG-MSNB-738-1B
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' SG-MSNB-739-1B SIRR-0809 , ..' !n SG-MSNB-736-1A-SIRR-0811 , ' ". SG-MSNB-737-1A' SIRR-0812 . RG-MSNB-252-1B SlRR-0810 FWSR-63 SIRR-0903 - s - ~r FWSR-61 SIRR-0808 , FWSR-64 CSRR-0376 A FWSR-66 CSRR-0437 i CSRR-0193 i ' CSRR-379 > CSRR-438 ' , , '
- 0bserved US Testing inspectors examining these supports.
i r j ,5NUBBER FUNCTIONAL TESTING OBSERVED . . SISR-424-B !
, [o J SISR-424-At !
.SISR-1278 , s
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