IR 05000275/1987007
| ML20212A293 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/12/1987 |
| From: | Burdoin J, Mendonca M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20212A190 | List: |
| References | |
| 50-275-87-07, 50-275-87-7, 50-323-87-06, 50-323-87-6, IEIN-86-025, IEIN-86-25, NUDOCS 8703030322 | |
| Download: ML20212A293 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
50-275/87-07, 50-323/87-06 Docket Nos.
50-275, 50-323 License Nos.
Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Facility Name:
Diablo Canyon Units 1 and 2
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Inspection at:
Diablo Canyon Site, San Luis Obispo County, CA Inspection Condu e.
Feb-ry 2
, 1987
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Inspector:
f.F.Burd'oin,R(actorInspection Date Signed Approved by:
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- l. M. Mendonca, Chief, Reactor Project Section I Date Signed l
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Summary:
Inspection During Period of February 2-6, 1987 (Report Nos. 50-275/87-07 and 50-323/87-06 Areas Inspected:
An unannounced inspection by one regional inspector of design, design changes and nodifications; followup of IE Notice (s) and Nonconformance Report (s) and an independent inspection of different vital
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areas and equipment in the plant.
Inspection Procedures Nos. 30703, 37700, 71707, and 92701 were used as guidance for the inspection.
Results:
No items of noncompliance or deviations were identified.
n 8703030322 G70212 PDR ADOCK 05000275 g
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DETAILS
- 1.
Individuals Contacted l
Pacific Gas and Electric Company (PG&E)
R. C. 'Thornberry, Plant Manager
- J. D. Townsend, Assistant Plant Manager, Support Services
- T. L. Grebel, Regulatory Cvinpliance Supervisor
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- D. A. Taggart, Director, Quality Support QA
- L. F. Womack, Operations Manager
- D. R. Bell, QC Supervisor, General Construction M. E. Leppke, Project Engineer, General Construction D. W. Shelley, Senior Nuclear Generation Engineer J. E. Nolan, Nuclear Engineer, Design Control E. Mendez, Administrative Supervisor S. M._ Brown, DCN Group Leader
. C. Schultz, Document Control Supervisor T. A. Roselli, QC Engineer G. R. Vincent, QC Inspector
M. W. Stephens, General Foreman, Instrumentation Various other engineering and QC personnel
- Denotes attendees at exit management meeting on February 6, 1987.
In addition, NRC Resident Inspectors attended the exit management meeting.
2.
Area Inspection An independent inspection was conducted in the Turbine and Auxiliary Buildings, Units 1 and 2.
The equipment and areas inspected included:
A.
Five Emergency Diesel Generator Rooms, Units 1 and 2.
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Six 4160 Volt Switchgear Rooms, Units 1 and 2.
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Combined Two-Unit Control Room, Units 1 and 2.
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Four Containment Spray Pumps.
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Five Charging Pumps.
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Four Safe Injection Pump Areas.
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Four RMR Pump Areas.
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Six Component Cooling Water Pumps.
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Six Auxiliary Feedwater Pumps.
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Housekeeping and equipment status appeared to be acceptable.
No violations of NPC requirements were identified.
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' Followup of IE Notice and Nonconformance' Report,
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A.
(Closed) 50-275/50-323'IE Notice 86-25 and Supplement 1, Traceability and Material Control of Material and-Equipment, Particularly Fasteners
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This notice made the licensee aware 6f.the poten'tially significant problems due to improperly marked fasteners.
This issue was identified during NRC inspections of licensee programs for control of materials and equipment.
The deficiencies in material traceability and control of fasteners were found at a number nuclear power plant construction sites.
This raised questions regarding the adequacy of controls to prevent the use of incorrect or defective fastener (bolts / nuts) materials.
The supplement to this notice identified a news release which expressed concerns about intentionally mismarked SAE J429K grade 8 bolts.
This intensified the concerns of the use of incorrect or defective fasteners.
The licensee conducted an audit of bolting at Diablo Canyon.
This audit inspected:
(1) Approximately 60 commercial grade fasteners and 150 high strength fasteners in the HVAC systems; (2) Over 350 fasteners in skid mounted pumps, pipe flanges, pipe supports, valves and heat exchangers; (3) Seventy-four fasteners in "Important to Quality" liquid radwaste system; and (4) Twenty fasteners in various electrical installations such as battery racks, cable tray, and supports.
The audit findings identified:
Three isolated occurrences involving the installation of ASTM A-307 low strength bolting in high strength application, and The widespread use of low strength bolting specified as ASTM A-307 without head markings.
The findings were dispositioned as follows:
The three isolated cases of wrong bolting material will be replaced per action request A0030697, A0030981, and QE A0003419.
NCR DC0-86-PG-N090 was issued to address the issue of unmarked bolts iri ASTM A-307 applications.
The root causes stated in the NCR were inadequate inspection and suppliers failing to provide material in conformance with the purchase order.
Tests of unmarked bolts installed in the plant have been planned as a
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result _of this NCR.
A procedure is in place with NECS-GC to remove a statistically, significant sample of bolts from the
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plant for destructive testing.
The tests will determine if the unmarked bolts meet the design requirements for an A-307 application.
The completion of these tests and the resolution of this NCR will address the unmarked bolt issue.
Testing of fasteners onsite is presently not part of the qualification program used at Diablo Canyon.
For safety-related uses, fasteners are purchased from suppliers on the qualified suppliers list (QSL), under procedure NPAP D-536, " Evaluation and Control of Suppliers." Per discussion with Diablo Canyon procurement, the licensee relies on the testing and QA programs of suppliers on the QSL to ensure that proper fasteners are provided.
Items with bolting marks that do not meet specifications are identified in the QC receipt inspection and documentation review process.
The Quality Support inspection of Diablo Canyon warehouse stock did not find any bolts without proper markings.
The current procurement practices address the concerns of the notice.
The inspector reviewed the licensee's documentation of the audit and the dispositioning of the audit findings and concludes they appear to be in proper order and adequate.
This IE Notice 86-25/ Supplement 1 is closed.
No violations or deviations were identified.
B.
(Clc3ed) Missed Surveillance on Radiation Monitor 1RM-48 The inspector examined Nonconformance Report DC1-86-TI-N151 prepared when it was realized Surveillance Test I-18AA was not performed at its prescribed time.
On November 24, 1986, with Unit 1 in refueling shutdown status Work Planning Center personnel, while attemptir.g to complete the recurring task for functionally testing Post Accident Sample System room area monitor 1RM-48, found that no functional test (STP I 18AA) data j
existed.
In discussions with the responsible personnel, it was l
determined that there are two possible causes for the data not being-j found.
The first possibility is that the test was performed and that l
after the daily status update was completed the data was lost.
The second possibility is that the daily status update was erroneously
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updated.
As the cause of the missing data is indeterminate the most conservative cause is assumed.
Therefore, it is considered that the test was not performed and that the daily status update was
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erroneously updated.
Following discovery of this omission, the test
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l was successfully performed on November 26, 1986.
As taking recurring l
task scheduler activities to complete status is a two independent step process and the second step being the one that discovered the
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error it was considered that no history search was necessary.
Improvements have been made in the document handlir orocess that i
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status update and the Work Plar.ning Center receiving the document for second verificatio'n.
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As this radiation monitor (1RM-48) is not a Technical Specification
'(TS)~ required chann'el and was in. service in an area which had no potential for use-(Unit shutdown), there is considered to be no
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safety significance.
The inspector examined the TSs to verify this monitor is not required
.for plant operations or accident monitoring.
The inspector reviewed the following' aspects.of.this issue with the instrumentation general foreman:
(1) The root cause was personnel error resulting from unfamiliarity
.with a newly implemented work accomplishment reporting system.
(2) This radiation monitor (IRM-48) is calibrated monthly along with monitors (RM 34 and-35) and as such is identified on Surveillance Test Plant I-18AA1.
(3). Corrective action to prevent recurrence included:
(a)
11 supervisors were made more familiar with the reporting
. system and (b)' Enhancements were made in the document handling process which reduced the time between initial work accomplishment reporting.and second verification.
The inspector concluded that the corrective measures were adequate.
This item is closed.
4.
(0 pen) Followup Item-50-275/323/87-05-01, Design, Design Changes and Modification The review and examination of the licensee's program for processing design, design changes and modifications at the Diablo Canyon site was continued by reviewing the following procedures:
A.
Procedure NPAP C-1, " Nuclear Power Plant Modification Program."
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Administrative, Procedure (AP) C-151, "0nsite Plant Modification B.
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Administration.
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Procedure NPAP C-4, " Bypass of Safety Functions and Control of Jumpers."
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Diablo Canyon Project, PI-17, " Document' Control Operating Instructions."
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The inspector examined the following design change packages (DCPs) and the associated QC documentation to confirm the above procedures:
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DCP-J-31783 - RHR Pressure Transmitter, Replacement l
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.DCP-E-35763 - 480 Volt System', Cabling
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DCP-J-25792 - Auxiliar9 Feedwater System, Temperature Sensing and Alarms
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DCP-M-35057 - Emergency 0-G, Air Receiver Press. Switch
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The DC packages and the associated QC documentation appeared to be in accordance with administrative procedure requirements.
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'The inspection of this item will be continued during a subsequent
inspection.
No violations or deviations were identified.
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5.
Exit Meeting.
The inspector conducted an exit meeting on February 6, 1987, with the Assistant Plant Manager and other members of the plant staff.
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meeting, the inspector summarized the scope of the inspection activities
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and reviewed the inspection findings as described in this report. The licensee acknowledged the concerns identified in the report.
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