IR 05000397/1987031
| ML17279A792 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/14/1988 |
| From: | Clark C, Johnson P, Obrien J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17279A790 | List: |
| References | |
| 50-397-87-31, NUDOCS 8802010196 | |
| Download: ML17279A792 (6) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
Docket No.
License No.
50-397/87-31 50-397 NPF-21 Licensee:
Washington Public Power Supply System P.
0.
Box 968 Richland, Washington 99352 Facility Name:
Washington Nuclear Project No.
2 (WNP-2)
Inspection at:
WNP-2 Site, Benton County, Washington Inspection conducted:
November 30 - December 18, 1987 Inspectors: ~
.
p.
rien, Reactor Inspector C.(I Approved By:
ark, Reactor Inspector
-'ffice inspection only)
Date Signed
//f8V Date Signed fs E'S'.
H.
React r hnson, Chief Projects Section
Date Signed Ins ection Summar
-Ins ection on November 30 - December 18 1987 Re ort No. 50-397/87-31 Areas Ins ected:
Routine project inspection in the areas of followup of inspector identified items, corrective action programs and an inoffice review of the latest inservice inspection report.
Inspection procedures 92701, 92720 and 90713 were covered.
Results:
Six inspection followup items were closed, and two remain open pending licensee action.
No violations or deviations were identified.
8S0~0>O>9S 8801>5 PDR ADQCK 05000397
P,DR
DETAILS 1.
Persons Contacted Licensee Personnel:
C.
M.
- J.
W.
- D. S.
"A. G.
- K. D.
- M. C.
R. L.
- G. J.
R. J.
- S
- Bil1 S.
C.
B. J.
Powers, Pl'ant Manager Baker, Assistant Plant Manager Feldman, Plant guality Assurance Manager Hosier, Nuclear Safety Assurance Group (NSAG) Manager Cowan, Plant Technical Manager Bartlett, Plant gC Supervisor Koenigs, Plant Technical Supervisor Kozlik, Shift Manager Barbee, Plant Engineering Supervisor Washington, Lead Compliance Engineer Milbrot, BPA Representative Denison, NSAG Engineer Hahn, Human Performance Evaluation System (HPES) Coordinator
Denotes those attending the final exit meeting on December 18, 1987.
The inspector also contacted licensee operators, engineers, technicians, and other personnel during the course of the inspection.
2.
Licensee Actions On Previous NRC Ins ection Findin s a.
Closed Followu Item 83-55-02)
Hi-Lo ressure interface and s ursous si na ana sos.
This item identified discrepancies in the control and implementation of the fire protection progam, and was to be addressed in the next FSAR change.
The lead compliance engineer provided copies of ammendments 37 and 38, that were submitted in August 1986 and August 1987.
Review of NRC records indicates that the amendments have not been approved by the NRC, and are pending further licensee action.
Also identified was the fact that this issue is being tracked by Inspection followup Item (86-25-01)
and Inspection Unresolved Item (86-25-08).
This item is administratively closed; however, the technical issue is still open, and will be tracked by the previously mentioned followup and unresolved items.
b.
Closed Followu Item 85-05-02
, Audit followu effectivness.
This item dealt with an insurance fire protection audit and a gA audit that identified the need for an additional fire protection engineer.
An additional fire protection engineer has been assigned.
This item is close Cl os ed Fol 1 owu Itern (85-11-05 Vendor Fi 1 es.
This item dealt with a review of the certified vendor information (CVI) files.
This review indicated that licensee actions had not been taken to assure that vendor technical information was being incorporated into the respective files.
Licensee management committed to a review of the Operating Experience Review files (e.g., Significant Operating Event Reports (SOER's),
GE Service Information Letters, vendor notices).
This review was complete, and identified a number of issues.
The inspect'or verfied that the required revisions to the CVI files were being implemented.
This review also identified a question concerning the response to IEB 80-09.
The issue was concerning the Rosemont pressure transmitters (model number 1151/1152) that required a circuit change for over-ranging protection for safety related applications.
This NSAG review of IEB files indicated that this circuit change had not occurred or the maintenance history for this equipment was inadequate.
The inspector verified that the licensee checked the equipment for the circuit change, that the circuit change was installed, and the appropriate documentation was entered in the equipment's maintenance history.
This item is closed.
Closed Followu Item 86-11-08 Locked Valve List Revision.
This item dealt with a disagreement between the Locked Valve List and the licensee's piping and instrument diagrams (PSIDs) for the Res'idual Heat Removal (RHR) System.
The inspector reviewed the Plant Operations Committee (POC) minutes (87-20),
and resulting revisions to these documents.
This item is closed.
Closed Followu Item (87-04-01 Pro ram for Valve Control for S ort S ut owns.
This item dealt with weaknesses in control of safety system valve lineups during short term outages.
The inspector reviewed revision
(dated 8/28/87) for procedure 1.3.8, Equipment Clearance and Tagging, related POC minutes, and documentation for the related Plant Deficency Report (PDR).
These documents showed that the licensee had provided appropriate operator training and had added the operators'og sheets.
This item is closed.
0 en Followu Item 87-11-01 Motor 0 crated Valve Test Pro ram.
This item dealt with the need to have the motor operated valve (MOV) test equipment entered into the Measuring and Test Equipment (MTE) Program.
The inspector verifi'ed that the MOV test equipment had been entered into the MTE program, and that the computerized tracking system will call out the equipment for calibration in February 1988.
However, the program further requires a unique identification of equipment with traceable records that have valid relationships to a nationally recognized standard such as the National Bureau of Standards.
Further review of the licensee's program indicated that the licensee did not have the capability to calibrate this equipment, nor had any arrangements
been made for having it done.
This item will remain open pending licensee resolution of this weakness in the program.
g.
(0 en)
Followu Item 87-21-01 Vital Maintenance Work Re uests MWRs This item provided a number of examples of weaknesses that were indicative of problems with the Vital MWR program.
The licensee committed to an evaluation of the program.
This evaluation was complete, and the inspector reviewed the POC minutes concerning the evaluation, presentation of concerns, and licensee management comments.
The incorporation of these comments into the applicable procedures was still in progress at the end of the inspection.
This item will be followed up during a later inspection.
h.
Closed Followu Item (87-25-01 Part 21 Review weaknesses.
This item identified a weakness, in procedure 1.10.4 concerning External Operational Experience Reviews in that it did not address
CFR part 21 reports received from external sources.
It was further.noted that a number of NCR's did not include a statement regarding Part 21 applicability.
The inspector reviewed changes to PPM 1. 10.4 and the gA manual (NOS-14) concerning this item.
The inspector also verfied that a note was added to all 1987 NCR's concerning Part 21 applicability.
This item is closed.
Within this area inspected, no violations or deviations were identified.
3.
Corrective Actions The inspector reviewed the licensee's program for Corrective Actions.
Appendix B to 10 CFR Part 50, Criterion XVI, and ANSI N18.7 - 1976 require the licensee to develop a
comprehensive program to identify, follow, and correct safety-related problems.
These documents further require.
that, for significant conditions adverse to quality, the cause, of the condition be determined and corrective action be taken to preclude repetition.
The inspector verified that the licensee has an adequate corrective action tracking system which considers inputs from:
a.
Operating Events (e.g.,
Licensee Event Reports, generic letters, and Information Notices)
b.
Internally Identified Problems (e.g.,
c.
gA Audits and Trending Programs d.
NRC Inspection findings e.
Employee Concern Programs (e.g., "Director's Hot Line")
f.
Special Reports by internal or outside organizations (e.g.,
owner's groups, INPO, industry task groups)
The inspector reviewed the following procedures:
PPM 1.3.12 - Plant Problems PPM 1.3.8
- Equipment Clearance and Tagging PPM 1.3.5
- Reactor Trip and Recovery PPM 1.3.45 - Human-Performance Evaluation System Program Additionally, the inspector interviewed program managers and key personnel involved in the these programs, reviewed four selected items from the above inputs and reviewed the licensee's handling of the issues.
The inspector found the licensee to have adequate programs to identify safety significant problems, determine reportablity, prioritize problems, establish corrective actions and responsibilities, consider potential generic concerns, consider the underlying "root causes" for human error problems, develop a method to follow corrective action to completion, determine if the corrective action is timely, and document completion of the corrective action.
No violations or deviations were identified.
Inoffice Review of Licensee Inservice Ins ection Re ort.
The inspector reviewed the NNP-2 "INSERVICE INSPECTION SUMMARY REPORT FOR REFUELING OUTAGE RF87A (Spring 1987)".
Some of the data discussed in this report had been previously reviewed by the inspector, as documented in NRC inspection report 50-397/87-10.
The information provided in this report met the reporting requirements of ASME section XI, Article IWA-6000,
"Records and Reports".
No violations or deviations were identified.
Plant Tour The inspector conducted a tour of facility buildings on December 2, 1987 with the NRC Senior Resident Inspector (SRI).
This was done to assess the licensee's housekeeping activities.
No violations or deviations were identified.
Exit Meetin On December 18, 1987, an exit meeting was held with the licensee representatives identified in paragraph 1.
The inspector summarized the inspection scope and findings as described in this report.