IR 05000382/1990003
| ML20006E754 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/09/1990 |
| From: | Barnes I, Gilbert L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20006E747 | List: |
| References | |
| 50-382-90-03, 50-382-90-3, NUDOCS 9002260316 | |
| Download: ML20006E754 (5) | |
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APPENDIX
[" 4 U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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lNRC Inspection Report: 50-382/90-03 Orerating License: NPF-38-
tiocket: 50-382 Licensee: - Louisiana Power & Light Company l'~
317 Baronne Street New Orleans, Louisiana 70160 n
~ WaterfordSteamElectric. Station, Unit 3(W3SES)
Facility Name:
Inspection At: Taft Louisiana-r Inspection Conducted: Manuary 29 through February 2,1990 e
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. Inspector:
. M Bu e 2 - v-9 o
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g-L..D. Gilbert,ReactorInspector, Materials Date
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and Quality Programs Section,- Division of Reactor Safety
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Approved:-
8-2 - y-7 o I. Barnes, Chief, Materials and Quality Date Programs Section, Division of Reactor Safety
- inspection Summary
' Inspection Conducted January 29 through February 2,1990 (Report 50-38?/90-03)
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Areas Inspected:~ Routine, announced inspection;of licensee action on
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previously identified inspection findings.
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Results:, Ten previously identified inspection findings were reviewed: eight
' were found to be satisfactory for closing, one was administrative 1y closed, and
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one was left open pending further review.
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b 9002260316 900213
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DETAILS 1.
PERSONS CONTACTED i
LP&L
- R. P. Barkhurst, Vice President,; Nuclear Operations
- A. S. Lockhart Nuclear Quality Assurance Manager
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- R. G. Azzarello, Nuclear Operations Engineering & Construction Manager
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- J. R. McGaha, Plant Manager - Nuclear y
- P. 'V. Prasankuman, Assistant Plant Manager - Technical Services
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- G. M. Davis, Manager - Events Analysis Reporting & Responses
- D. F. Packer, Assistant Plant Manager - Operations & Maintenance
- D. E. Baker, Nuclear Operations Support & Assessment Manager
- L. L. Bass Nuclear Operations Engineering & Construction
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- T. H. Smith, Plant Engineering Superintendent l-
- P. M. Melancon, Reactor Engineering Supervisor l
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- *L. W. Laughlin, site Licensing Supervisor L.
D. V. Gallodoro, Procurement Engineering Supervisor
'J. Sleger, Jr., Safety Review Committee Manager i
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E. B. Hyatt, Safety Review Committee Coordinator
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i J. Holman, Nuclear Operations Engineering & Construction
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D. Grubic, Licensing NRC
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- R. C. Haag, ANO Resident Inspector The inspector also interviewed other licensee employees during the inspection.
- Denotes attendance at exit interview conducted on February 2,1990
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L 2.
LICENSEE ACTION ON PREVIOUSLY IDENTIFIED ITEMS (92701 AND 92702)
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2.1~(Closed) Violation (382/8902-01):
Failure to use stud material specified on drawing.
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The inspector verified that the quality notice (QA-89-037) used to track this'
item had been properly closed by the licensee. The inspector reviewed the work authorization (WA 01033177) that documented the engineering evaluation supporting L-the operability determination for the incorrectly installed material. The work authorization also documented that the incorrect material has been replaced
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with the material specified on the drawing. The inspector also verified that
Administrative Procedure MD-1-014, " Conduct of Maintenance," has been revised
to provide specific instructions regarding actions to take when the needed information cannot be determined because of an unclear drawing. This item is
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closed.
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2.2 (Closed) Violation (382/8902-02): Failure is impose 10 CFR Part 21 on a. vendor.
-The inspector reviewed changes to the procurement process which have been incorporated into the Nuclear Operations Engineering & Construction (N0EC)
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Procedure N0ECP-004, "The Engineering Procurement Process," Revision 0, and.
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Instruction N0ECI-152, " Safety-Related Procurement Methods," Revision 1.
The procurement process and methods of N0ECP-004 and N0ECI-152 now provide comprehensive directions for the procurement engineers with regard to imposing L,
10 CFR Part 21 on vendors. The inspector also verified that-the Okonite Company had been added to the LP&L qualified suppliers list for comercial
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grade suppliers. The basis for adding the Okonite Company was a quality
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' assurance surveillance performed at the company on April 7,1989. LP&L
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specified an expiration date of April 7,1991, for the current qualification.
This item is closed.
2.3 (closed) Violation (382/8907-01):
Failure of Safety Review Committee (SRC)
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l to review safety evaluations.
E The inspector discussed this violation with the SRC Manager and the SRC Coordinator.
The inspector was informed that the four safety evaluations specified in the r
L violation, which had not received SRC review, had been located and reviewed by the SRC. The inspector verified that the SRC review had been performed and
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documented by. reviewing the SRC Meeting Minutes for July 1989 and January 1990
with the' attached SRC Review Subcommittee Meeting Minutes. The inspector was
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informed that the controlling procedure for review of safety evaluations is now Nuclear Operations Procedure NOP-013. "10CFR50.59 Safety and Environmental
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Impact Evaluations," Revision 1.0, which has an effective date of January 1 1990.. This1 procedure directs supervisors to transmit a copy of all safety
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evaluations, including revisions, to the SRC Secretary. The safety evaluations I
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are being logged and numbered by the SRC Secretary and distributed to the Plant Operations Review Committee (PORC) and other eppropriate groups. The inspector
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also reviewed the changes to Administrative Procedure UNT-1-004, " Plant Operations Review Committee," and Nuclear Operations Engineering and Construction
Procedure N0ECP-005, " Preparation of 10CFR50.59 Safety and Environmental Impact
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Evaluations," which direct PORC and the Design Engineering Coordinator Group L.
Leader to transmit safety evaluations to the SRC.
In addition to the above
controls, the~ SRC Secretary, who is also the SRC Manager, coordinates with PORC to ensure that all safety evaluations are sent to SRC for review. This item is closed.
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~ 2.4 (Closed) Followup Item (382/8907-04): Review of 50.59 evaluations of
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l revised station modifications,
l-The inspector discussed this issue with the SRC Manager / Secretary and Coordinator
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and confirmed that Station Modification Packages SMP 0097, 0441, 0502, 0804, i
1215,1427, and 1494 including all revisions containing safety evaluations have
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'been reviewed by the SRC. This item is closed.
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-4-2.5 (Closed) Violation (382/8907-03): Failure to identify and control limited shelf-life materials.
The inspector verified that the licensee has established comprehensive shelf-life controls in Administrative Procedure UNT-8-015. " Shelf Life Program," Revision 0.
~The inspector also reviewed the corrective action taken by the licensee to identify those items in the existing inventory which potentially required shelf-life-controls. A computer printout identified 2,187 items in this category which should be evaluated for assigning shelf-life controls. Procurement Engineering performed the evaluation using the criteria established in Procedure UNT-8-015 and the services of a contractor, Digital Engineering, Inc.
On completion of the evaluations, Operations Quality Assurance personnel verified on a sampling basis, as documented in Quality Notice QA-87-071, that the evaluations.had been completed and were being entered into the Material L
Management Information System. The procurement engineering supervisor informed the inspector that the shelf-life controls from the evaluation sheets have been completed. The inspector selected items from the beginning, middle, and end of the list of items required to be evaluated and verified that the Material Management Information System now contains shelf-life controls for the items.
This item is closed.
2.6 (Closed) Violation (382/8531-03):
Failure to evaluate and report a defect to NRC.
The hardware portion of this violation was previously verified to have been l
satisfactorily addressed (i.e., NRC Inspection Report 50-382/88-26). However,
the issue of reportability under 10 CFR Part 21 had not been resolved. As a
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result of the failure analysis performed by the General Electric Company (GE),
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the GE maintenance manual (GEK-644598) was revised to provide additional instructions for checking and correcting the torque on the contact adjusting
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screw during maintenance of the AKR-30 and AKR-50 circuit breakers.
In order
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to resolve GE's generic concern, the revised maintenance procedures were j
transmitted to all potentially affected utilities to preclude having similar problems. The licensee's maintenance procedure, ME-4-145, "480 G.E. Switchgear Breaker," Revision 7 has been upgraded to include the revised maintenance procedure provided by GE. Since the GE maintenance manuals have been revised and transmitted to potentially affected utilities, the reportability issue becomes moot. Therefore, this item is being closed.
2.7.(Closed)Unresolveditem(382/8932-02):
Possible stress risers in piping.
The inspector reviewed the design engineering evaluation, which was documented in Problem Evaluation /Information Request (PEIR) No. 10820. The design engineering i
evaluation included visual examination, design calculations, and liquid penetrant examination of the-indentation on Weld 50-056 in the low pressure safety injection Pump B suction line of Unit 2.
Based on the evaluation by design engineering that the condition was acceptable, this item is resolved.
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-5-I 2.8.(Closed)UnresolvedItem(382/8918-01): Corrective action for radiological posting deficiencies.
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The inspector reviewed the corrective action portion of the radiological deficiency reports issued during 1989 for radiological posting discrepancies
and noted that the corrective actions were documented as required by Administrative Procedure HP-1-112. To ensure wide spread dissemination, a discussion of the i
requirements for radiological posting was included in the monthly department i
group safety meeting. Since the discussions in the August safety meetings, no posting discrepancies have been reported by health physics personnel. This item t
is resolved.
2.9 (0 pen) Unresolved Item (382/8930-03): Procurement of gas tungsten arc welding filler materig.
This item will remain open pending the licensee's review and listing of all
welding filler material purchase orders and welding procedure specifications i
that were used for gas tungsten arc welding filler material. The NRC will review this listing to determine compliance with ASME Section III.
2.10 (Closed) Followup Item (382/8902-04):
Implementation of 10 CFR Part 21
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The licensee has reviewed and clarified Administrative Procedure UNT-006-015
" Identification, Evaluation and Reporting of Defects and Noncompliances under 10CFR21." The procedure has been revistd to include those 10 CFR Part 21 reports received from external sources in the loggir,g of Part 21 reports. This item is closed.
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EXIT INTERVIEW An exit interview was conducted on February 2, 1990, with those personnel denoted in paragraph 1 in which the inspection findings were summarized. No information
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was presented to the inspector that was identified by the licensee as proprietary.
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