IR 05000269/1986008
| ML20205M748 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/02/1986 |
| From: | Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205M734 | List: |
| References | |
| 50-269-86-08, 50-269-86-8, 50-270-86-08, 50-270-86-8, 50-287-86-08, 50-287-86-8, IEB-82-02, IEB-82-2, NUDOCS 8604150366 | |
| Download: ML20205M748 (6) | |
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QCEGu UNITED STATES i
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NUCLEAR REGULATORY COMMISSION -
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REGION ll
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101 MARIETTA STREET, N.W.
2-ATLANTA, GEORGI A 30323
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Report Nos.: 50-269/86-08, 50-270/86-08, and 50-287/86-08 l
Licensee: Duke Power Company
422 South Church Street Charlotte, NC 28242
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Docket Nos.: 50-269, 50-270, and 50-287 License Nos.:
I Facility Name: Oconee 1, 2, and 3 Inspection Conducted: March 3-7, 1986 l
Inspector:
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i N. Economos '
/Date Signed Md Approved by:
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g J. J. Blake, Section Chief
/*Date' Signed Engineering Branch
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Division of Reactor Safety
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SUMMARY
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i Scope:
This routine, unannounced inspection entailed 39' inspector-hours ~ in the -
i areas of Unit 1 eddy current examination (EC)l of' once through steam generator (OTSG) tubes; sludge cleaning of OSTG(s) by the Water Sla of the reactor vessel level instrumentation system (RVLIS)p method; installation
l Unit 3; closing of open items.
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Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- M. S. Tuckman, Station Manager
- R. J. Brackett, Senior Quality Assurance (QA) Engineer S. Lynch, Assistant Engineer, Project Services M. Hipps, Assistant Engineer, Technical Support E. Few, Engineering Specialist W. R. Hunt, ISI (Inservice Inspection) Coordinator M. McAllister, Technical Support C. Payne, Technical Support, RVLIS Accountability C. P. Tegard, Design Engineer, Cholotte
- T. C. Matthews, Compliance Other Organizations Babcock and Wilcox (B&W), Special Products and Integrated Field Services H. E. Stopplemann, ISI Coordinator l
NRC Resident Inspectors
- J. C. Bryant, Senior Resident Inspector
- K. Sasser, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 7,1986, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected. No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (Closed) Violation 269,270,287/85-27-01, Failure to use properly qualified welding procedure.
The licensee's letter of response dated October 31, 1985, has been reviewed
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and determined acceptable by Region II. The inspector held discussions with the Technical Support Engineer and examined the corrective actions as stated in the letter of response.
The inspector concluded th:t the licensee had
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r determined that full extent of the subject noncompliance, performed the
necessary followup actions to correct the present conditions, and developed l.
the necessary corrective actions.
The corrective actions identified in the
letter of response have been implemented.
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(Closed) Violation 269,270,287/85-27-02, Use of filler metal which had not j
been tested per code requirements.
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The licensee's letter of response dated October 31, 1985, has been reviewed l
and determined acceptable by Region II. The inspector held discussions with
the Technical Support Engineer and examined the corrective actions as stated in the letter of response. The inspector concluded that the licensee had li determined the full extent of the subject noncompliance, performed the necessary followup actions to correct the present conditions, and developed
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The corrective actions identified in the letter of. response.have been implemented.
(Closed) Violation 270/85-27-03, Failure to obtain QA approval on RC pump replacement studs, prior to Unit 2 startup.
The licensee's letter of response dated October 31, 1985, has.been reviewed
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and determined acceptable by Region II. The inspector held discussions with the Technical Support Engineer and examined the corrective actions as stated
in the letter of response.
The inspector concluded that the licensee had j
determined the full extent of the subject noncompliance, performed the
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necessary followup actions to correct the present conditions, and developed the necessary corrective conditions.
The corrective actions identified in i
the letter of response have been implemented.
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Unresolved Items
Unresolved items were not identified during this inspection.
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IE Bulletin 82-02: Degradation of Threaded Fasteners in the Reactor Coolant i
Pressure Boundary of PWR Plants, Unit 3 (92703B)
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Temporary Instruction (TI). 2515/71, Inspection of licensee's actions in response to IE Bulletin 82-02 contain inspection recommendations which were generated.because of above normal number of occurrences of -leaking connections reported from recent inspections.
The areas ' earmarked for inspection included (1) review of maintenance _ procedures for-threaded i
fasteners in components of the reactor coolant pressure boundary (RCPB) and-(2) review of QA measures to minimize susceptibility to s. stress corrosion cracking (SCC) environments from -lubricants for threaded fasteners.
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i components, maintenance procedures and the lubricants: designated for their threaded fasteners were as follows:
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Item Maintenance Procedure Designated Lubricant
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' Reactor Coolant Pump MP/2/3/A1310/22 Fel-Pro-N5000 QA Grade Closure Studs
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OTSG Primary Side MP/0/A - 1130/2A Fel-Pro-N5000 QA Grade Manways and Hanhole Covers, Removal and Replacement Low Pressure Safety MP/0/A - 1200/26&A Neolube Injection Valves 1 & 2
Pressurizer Heater MP/0/A - 1120-1 Molykwte-G
Removal and Installation By review of procedures, records, procurement documents, certified material test reports and through discussions with cognizant personnel, the inspector determined that applicable torque valves and the lubricants presently applied to the fasteners are consistent with manufacturer's recommendations.
Station Directive 2.4.5 " Control of Surface Applied Material Using the Power
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Chemistry Materials Guide," is used by the licensee to convey responsibili-l ties for the procurement, selection, storage and use of new and existing storage and use of new and existing surface applied material use at Oconee.
The Power Chemistry Materials Guide referenced in the aforementioned
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Directive contains chemical analyses of the aforementioned lubricants and specifies the acceptable ranges of halogens, i.e., chlorides and in the case of molydesulfide (MoS ) the sulphur content. Although these lubricants are
"off the shelf" items, their procurement and control appear.to meet the intent of ANS-3.2-1982, paragraph 5.2.13 " Procurement and Material Controls."
Within the areas inspected, no deviations or violations were identified.
6.
Installation of Reactor Vessel Level Instrumentation System (RVLIS) - TMI Action Item, Unit 1(92706/37700)
Work on the RVLIS modification was underway at the time of this inspection.
The system was designed by Westinghouse (W) who is presently overseeing the installation that is being done by the licensee.
Station modification ONSM-12401, Revision 2, Inadequate Core Cooling Monitoring System is the controlling document of this work effort. By review of applicable drawings,
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and through discussions with cognizant personnel, the inspector ascertained that system design and materials, with the exception of the 3/4 inch Rockwell manual isolation root valve, conform to ASME.Section III (80W82)
requirements.
The valve conforms to the 1974 Edition with Summer 1975
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Installation / fabrication requirements, i.e.,
weld fabrication and examination, comply with original construction code-(B31.7-69) requirements.
The system wtT1 be tested in accordance with ASME
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Section XI (80W80) requirements.
Licensee documents / drawings reviewed were
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as follows:
Engineering Justification Report, #ECPG-JR-1 Rev. 1 Drawing #0-4221-7.01 Rev. D
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Drawing #0-4221-7.02 Rev. C Drawing #0-4221-7.03 Rev. D, Field Installation Standard for 3/16" tubing Drawing #422.04-01 Rev. F Reactor Vessel Level Monitoring System At the licensee's fab shop, the following completed welds were inspected for conformance with applicable code requirements:
ISO RC-95 Decay Heat Drop Line B Weld Description
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Valve to Coupling
Valve to Pipe
Valve to Tubing Adapter ISO RC-94 Decay Heat Drop Line A Weld Description Condition l
Valve to Coupling Completed
Valve to Pipe Completed
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Valve to Tubing Adapter Completed Quality records were reviewed for the following items:
Valves S/N QA Tag WQR#
Rockwell, 3/4" BZ501 48427 N-72882 Rev. O T-78 Root Valve BX050 48427 N-72882 Rev. O Couplings W4LZK 47415 Tubing Adapter 8640 47071 Pipe 3/4" Sched.
HT-455663 42588 l
160 Height Volume ILIS-1310 N-75082 Rev. 0 Sensors
Model #353 ILIS-1311 N-75082 Rev. 0 ILIS-1320 N-75082 Rev. 0 ILIS-1321 N-75082 Rev. 0
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Filler Metal
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3/32 ER-308 HT-#P2716 46460-
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For the above items, quality records reviewed included Westinghouse quality releases (QR(s)), code date reports certified material test reports, receipt inspections reports, weld fabrication records, welder and QC inspector qualifications, weld procedure qualifications as applicable.
In addition, the inspector walked through the reactor building to observe housekeeping conditions and observed the routing of installed segments of the A&B trains of the system. Segments observed were those attached to the refueling canal liner and vertical and horizontal runs attached to the containment liner plate leading to the decay heat drop line, the hot leg (candy cane) and the containment penetrations.
Within the areas inspected, no deviations or violations were identified.
7.
Eddy Current Examination of Once Through Steam Generator (OTSG) Tubes, Unit 1 (73753)
This is a followup to the work effort in this area documented in Report 50-269/86-03.
Preliminary results of the eddy current examination of 0TSGs
"A" and "B" disclosed that four tubes in "A" exceeded code allowable (40%)
wall degradation and will require plugging.
Similarly there were fourty-two (42) tubes in OTSG "B" that will require plugging. As required by Technical Specification 4.17.6(a), following completion of this outage, the licensee will furnish the Region, by report, the exact number of tubes taken out of service.
Within the areas inspected, no violations or deviations were identified.
8.
Sludge Cleaning of 0TSG by Water Slapping Method, Unit 1 (92706/62702)
Cleaning of the secondary side of OTSG "A" commenced at the time of this inspection.
The process " water slapping", involves the injection of nitrogen under high pressure e.g. 1100-1200 psig, into the secondary side of i
the OTSG, to force the water previously pumped into the generator to " slap" up against and through the broached tube support plate holes and other water passages.
The force of the water slap, dislodges the residue deposits from the water passages between the tubes and tube supports plates which tends to enhance OTSG performance.
The resulting loosened sludge is subsequently removed by sludge lancing and other sludge removal methods.
The inspector observed the activity, that was being conducted by B&W under contract with DPC, and viewed a video tape presentation depicting condition inside the OTSG "A" following completion of this process. A more detailed description of this activity and process is discussed in Region II report 50-259/86-09.
Discussions with cognizant contractor and licensee personnel disclosed that overall residue concentrating on the support plates were reduced down to the point where water passages were now approximately 80% sludge free.
Within the areas inspected, no deviations or violations were identified.
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