IR 05000382/1982005
| ML20052F970 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/14/1982 |
| From: | Crossman W, Martin L, Schum W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20052F958 | List: |
| References | |
| 50-382-82-05, 50-382-82-5, NUDOCS 8205140199 | |
| Download: ML20052F970 (13) | |
Text
{{#Wiki_filter:g . APPENDIX B U. S. NUCLEAR REGULATORY COPEISSION
REGION IV
NRC Inspection Report: 50-382/82-05 Licensee: Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana .70174 Facility: Waterford Steam Electric Station, Unit 3 Inspection At: Taft, Louisiana Inspection Conducted: March 1-5, 1982 Inspectors: / //) JN' 9$$W//2 L. ~Er Martin 1Fehctor Inspector Dirte 7 Reactor Pro' ct Section B (Paragraphs 8, 9, 10, & 11) ~ YY Y Nb2 /h ' - W. S..Schum, Reactor Inspector Date ' Reactor Project Section~B (Paragraphs 1, 2, 3, 4, 5',t6, & 7) > . ' Approved: [ M//Ah'A p W.' W. Cross an, Chief; Ddte/ , ) Reactor Pr fect Section B d , Inspection Stimary },.. ~ Inspection on March 1-5, 1982 (Report 50-382/82-05) Areas Inspected: Routine, unannounced inspection of licensee action on previous inspection findings; licensee identified items; housekeeping; reactor vessel and internals; review of Tompkins-Beckwith audits performed by LP&L and EBASC0; review of records of safety-related piping and as-built conditions; mechanical / electrical installed equipment; and primary system piping installation.
The inspection involved 73 inspector-hours by two NRC inspectors.
Results: Of the eight areas inspected, three violations were identified in two of the areas.
Two violations were identified in the area of reactor vessel and internals (paragraph 5),and one violation was identified in the area of mechanical / electrical installed equipment (paragraph 8).
8205140199 820427
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DETAILS-1.
Persons Contacted Principal Licensee Employees L. Bass, Project QA Engineer
- R. Bennett, QA Engineer
- T. Gerrets,-QA Manager
- G. Koehler, QA Engineer
- R. Sandridge, QA Engineer
- J. Woods, QC Engineer
- W. Morgan, OSP QA,
- L. Arnold, Waterford-3 Startup Group
- P..Prasankumar, Maintenance Superintendent
- C. Decareaux, Construction Engineer
- D. Lester, Plant Manager I
Other Personnel ,
- B. Tarrant, Mechanical Superintendent, EBASCO
- T. Kopac, Site Manager, NISCO
- L. Stinson, Manager, Site Quality PGM, EBASCO
The NRC inspectors also interviewed other contractor personnel.
.
- Denotes those attending exit interview.
. 2.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation 50-382/81-29: ' Failure to follow procedures for , protection of electrical penetration assemblies.
<The NRC inspector revieted records and inspected electrical penetra-i l tions for protection. -The records and physical conditions were satis f actory.
The licensee has increased CMI requirements to a weekly frequency.
- They are also performing nightly inspections for the protection and cleanliness of all the penetrations.
This item is considered closed.
- - b.
(Closed) Violation-81-05A (T-B): Failure to continue corrective i action commitment 80-06 with regard to protection of containment-penetrations.
Licensee appears to be in compliance with commitment and this item is considered closed.
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3.
Licensee Action on Previously Reported Items a.
(Closed) CDR No. 24 - Defective valve manual operators.
The defective operators had a cast iron gear replaced with a silcon bronze gear, increasing the torque capacity.
< This item is considered closed.
! b.
(Closed) CDR No. 22 - Inadequate electrica1' insulation on Excore . Neutron Flux Detectors.
The.NRC inspector reviewed data associated ' the with final report including CE letter'of August 7, 1981, M&TE Calibration Documents,.CE QA Document Package, and Insulation Rewrap Travelers.
These documents will assure-proper control of electrical-insulation and excore;NFDs.
' < This item is considered closed.
c.
(Closed) Potential CDR No. 48 - Flammability / solubility deficiency of Quelube cable pulling lubricant..Although'not a reportable item, i this potential CDR was reviewed with.the following finding: Vertical and horizontal tests were run with varying loadings in both tray and conduit configurations using the alternate ' flame method from IEEE 383 74. -The testing was performed at QuelubefacilitiesinAugusthof198}F,thetestsshoweditwill Although Quelube has an . ignition point of approximately 825 not sustain combustion when in any of the test configurations and no cable damage was caused by flammability of Quelube.
This item is considered closed.
d.
(Closed) CDR No. 21 - Linear indications in electrical cable tray , ' seismic support clips.
Review by the NRC inspector of the documenta-tion associated with this CDR showed that the problem with_the 88R1 ' clips first appeared in 1977.
Indications appeared after UT-inspections were performed as the' clips were cut for fabrication.
During fabrication activities, it was noticed that laminar indications were visible.
After discovery, considerable investigation and research were done.
Due to the physical condition of the suspect clips (galvanized), it was assumed they could be readily identified if significant problems did exist, and approximately 60-70 clips were installed on two levels of the RAB.' During later operations, all the clips were painted and it is presently not possible to determine which clips were from the heat number showing these indica-tions.
Due to the amount of effort expended, the NRC was notified i of a 50.55(e) deficiency on November 27, 1980.
In order to determine the magnitude of the problem, a test mock-up was made using seven , different worst case hanger configurations.
This mock-up was sent
to Construction Technology Laboratories for evaluation.
The testing
demonstrated that the clips were within Code limits for loading under worst case conditions and were, therefore, acceptaDie in the , installed location.
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.
This item is considered closed.
4.
Site Tour The NRC inspectors toured the Auxiliary Building, Turbine Building, Reactor Building, and control room to observe the ongoing construction, testing, maintenance, and housekeeping.
During the course of the tour, two items of nonconformance were identified as addressed in paragraph 5.
In addition, it was discovered that the control room supervisor was not being kept informed of all significant activities occurring on the site.
In particular, he was not. informed of a worker removed by site ambulance from the Reactor Building to the site dispensary.
The NRC inspector was subsequently informed that a draft procedure dealing with this subject would soon be promulgated.
5.
Reactor Vessel and Internals Care and Maintenance The NRC inspectors reviewed the care and maintenance requirements for the reactor vessel and internals.
10 CFR 50, Appendix B, Crterion V, states, "that activities affecting quality shall be... accomplished in accordance with these instructions, procedures...." EBASCO Care and Maintenance Instructions No. 33, Revision 7, and No. 37, Revision 3, require varying degrees of cleanliness and varying work zones and cleanliness requirements. These requirements change at different points of contruction, and storage locations.
Basically, a covering is required for the reactor and its internals with access controls afforded the vessel and its components.
The following conditions were identified: a.
The reactor vessel had " Fish Net" type covering only.
b.
The reactor core barrel was-not covered.
c.
The access control watch was reading a book and did not see the NRC inspector to prevent,his access to reactor refueling canal and components.
d.
The reactor upper internals were not covered and-access controls were not in force.
e.
The reactor head was not covered and access controls were not in force.
f.
Two control element drive mechanisms were open to the atmospher. .
In addition, during the inspection it was;noted that considerable dirt had accumulated on all exposed surfaces.and.within several improperly closed openings of the reactor head.
Sand blasting, welding and.similar construction activities were in progress.
' This is a violation.
The review of daily NISCO Housekeeping. audit's re' veal'ed that unsatisfactory cleanliness conditions had been identified a significant number of times since July 31, 1981, with no apparent effort being made to correct this condi tion.
, ~. Criterion XVI of 10 CFR 50, Appendix B, statss, "...-measures shall be established to assure conditions adverse to quality are promptly identified and corrected."
- ' This is a violation.
- 6.
Review of Quality Assurance' Records on Safety Related Piping a.
A review of audits conducted by LP&L and 'EBASCO of Tompkins-Beckwith (T-B) was performed by the NRC inspector.
The review was to ensure the completeness of audit scope, frequency of audits, and QA records of safety-related piping installed by T-B.
The NRC inspector reviewed nine audits done by LP&L, and seven audits conducted by EBASCO of T-B operations and procedures.
These audits inspected are: LP&L Audits: W35-82-75 W35-82-65 W3S-82-155 W35-81-7 W35-81-1S W35-80-14S W35-80-155 W35-80-1S W35-80-6 EBAS_C0 Audit:s 81-5-3 QA Record Control.
81-9-5 QA Manual Section VII.
81-9-6 Class I Piping Marking.
81-9-7 Control of Material.
81-8-1 Housekeeping.
81-4-2 Weld and Brazing Quatification Procedures.
81-2-4 Document Control.
No violations or deviations were identified during this review.
-
.
b.~ The NRC inspector reviewed several random T-B QA_ records to ensure compliance with QA recordkeeping procedures.
The inspector reviewed two weld travelers and approximately 60 nonconformance reports.- The nonconformance reports appear to contain no significant problems.
However, review of the weld travelers left one unresolved item.
In the review of the traveler-on isometric-1C-47-4T-FE, weld FW 15RW1 showed two heat numbers on the socket.
Pursuit of this led to many questions for which there was insufficient time to receive' answers.
This will remain an unresolved item pending further information and review'of'the material.
During the above review, it also was noted that two procedures were in existence.for the control of nonconforming material. release.
Once identified, one procedure was cancelled and removed from the controlled copy libraries throughout LP&L and EBASCO.
7.
Primary System Piping Installation The NRC inspector inspected primary system' piping installation during the inspection.
It was noted that nine RTD:thermowell's were nonconforming and were to be installed.. The i_nspector reviewed the control of this operation, welding procedures, and recordkeeping associated with this work.
NISCO appears ~to have good control of the placement of this material in the primary system.
The NCR associated with this matefial applies to damaged ID threads for RTD insertion. The wells are being installed to permit Cold Hydro Static Testing and are to be replaced with new wells when received pursuant to 1AW4400.b.5. Winter 1980 Addenda.
8.
Electrical / Mechanical Equipment Installation The NRC inspector reviewed procedures, records, and inspected portions of-the completed installation of HFSI dA" pump and motor, LPSI "A" pump and motor, and CCW Pump "A" pump and motor.
This review and inspection was performed to determine if the equipment was installed in accordance with the FSAR, design, and procedural requirements.
1he-following documents were reviewed: MC-1 " General Specification for Installation of Mechanical Equipment," Revision 1 ME-4-702 " Maintenance Procedure for Roiitine Electrical Maintenance during Construction Phases," Revisio'n 0.
Gulf Engineering Maintenance Records for preceding 8 month Gulf Engineering Travelers - PS-645, PS-154, PS-401, PS-107, PS-163, and PS-597 The inspector also reviewed 22 Condition Identification Work Authorizations (CIWA), 20 Nonconformance Reports (NCR), 11 Field Change Requests (FCR), and 2 Requests for Information (RFI).
During the course of this inspection, the NRC inspector attempted to locate the responsible individuals and records for the maintenance of equipment that had been released to LP&L for testing.
It became apparent that LP&L did have an organization and procedures in place and had not started implementation of this program even though they had been accepting equipment and systems for several months.
10 CFR 50, Appendix B, Criterion V, requires that activities affecting quality shall be performed in accordance with the prescribed instructions and procedures.
LP&L Procedure ME-4-702, Revision 0, Paragraph 8.1.5, requires the meggering of motors (50 HP and above) that have or will be idle for at least 1 month.
Gulf Engineering Equipment Maintenance records for CCW Pump Motors, HPSI Pump Motors, and LPSI Pump Motors require monthly meggering of the motors after October 26, 1981.
Contrary to the above: ' The NRC inspector's review of maintenance and startup records on March 3 and 4, 1982, revealed that HPSI system (60A) and the LPSI system (608) were released to LP&L without the periodic maintenance requirements (megger testing) being current.
After release to LP&L, the maintenance requirements (monthly megger testing) were not performed at the appropriate intervals for the HPSI, LPSI, and CCW pump motors.
The maintenance and startup records for these motors indicated the following information: 1Last Megger
Release Test Prior To Megger Test Motor To LP&L Release After Release HPSIA 12/1/81 4/19/81 2/10/82 HPSIB 12/1/81 4/19/81 2/12/82 HPSIAB 12/1/81 4/19/81 1/14/82 .
. __ - .
ILast Megger .p Release Test Prior To Megger. Test Motor To LP&L
- Release After Release LPSIA 2/2/82 10/13/81 2/7/82 LPSIB 2/2/82 10/13/81'
2/7/82 CCWA 11/23/81 4/81 ' 12/15/81
! CCWB 11/23/81 4/81 1/18/82 CCWAB 11/23/81
- '-
4/81 12/18/82 1 Frequency changid from semiannually to monthly on.0ctober 26, 1981.
2 Megger testing rel ted to startup' requirements but not recorded for maintenance.
LP&L Startup Group indicated that even though ME-4-702 existe'd, they had not initiated the maintenance program to the date of this inspection.
a This is a violation.
9.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations. One new unresolved item disclosed during the inspection is discussed in paragraph 6.
10.
Exit Meeting The NRC inspectors met with T. F. Gerrets and other licensee and contrac-tor personnel on March 5, 1982, to discuss the scope and findings of this inspection.
The violations identified in this report were acknowledged by the licensee representatives.
11. Management Meeting On April 7,1982, Messrs. G. L. Madsen, W. A. Crossman, G. L. Constable, J. E. Cummins, and L. E. Martin of the NRC Region IV staff met with
G. D. McLendon and other members of the LP&L staff.
The Region IV staff discussed equipment care,-maintenance, and startup test control concerns.
(See NRC Inspection Report 50-382/82-10 for details of this meeting.)
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