IR 05000254/1987017
| ML20236M240 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/03/1987 |
| From: | Gardner R, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236M223 | List: |
| References | |
| 50-254-87-17, 50-265-87-17, GL-83-28, NUDOCS 8708100517 | |
| Download: ML20236M240 (6) | |
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i U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-254/87017(DRS);50-265/87017(DRS)
Docket Nos. 50-254; 50-265 Licenses No. DPR-29; No. DPR-30 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station, Units 1 and 2 Inspection At: Quad Cities Site, Cordova, Illinois Inspection Conducted: July 7-24, 1987 f.h. h 'd b)ll87 l
Inspector:
J. H. Neisler I
Date
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,l3I l lS Approved By:
R. N. Gardner, Chief ol Plant Systems Section Da te Inspection Summary Inspection on July 7-24, 1987 (Reports No. 50-254/87017(DRS);
No. 50-265/87017(DRS))
Areas Inspected: Routine, announced inspection of licensee's action on previous inspection findings and review of the licensee's implementation of Generic Letter 83-28 in the areas of equipment classification, vendor interface, post maintenance testing, and reactor trip system reliability. This inspection closed TI2515/64R1 and TI2515/91.
(255648,92701)
Resul ts: No violations or deviations were identified.
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PDR ADOCK 05000254 G
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DETAILS
1.
Persons Contacted Principle Licensee Employees
- R. Bax, Station Manager
- D. Gibson, Quality Assurance Superintendent J. Reed, Technical Staff
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T. Crippes, Technical Staff R. Rustick, Technical Staff
- R. Robey, Services Superintendent H. Do, Technical Staff
- E. Weinfurter, Technical Staff K. Strain, Electrical Maintenance Foreman M. Kooi, Regulatory Assurance Supervisor A. Scott, Quality Assurance Engineer
- Denotes those persons attending exit interview.
2.
Licensee Actions on Previously Identified Items (Closed) Unresolved Item (50-254/87015-01; 50-265/84014-01): Additional controls for vendors not having a QA program. The inspector reviewed Procedures QP4-51, Attachment A, Revision 20, "Specifying Quality Assurance Documentation, and QP18-52, Revision 21, " Audit and Surveillance of Maintenance, Spare Parts, and Inservice Inspection Activities." The latest revisions of these procedures adequately provide for audits and evaluations of vendors who do not have a Commonwealth Edison approved Quality Assurance Program. This item is closed.
(Closed) Unresolved Item (50-254/84015-02; 50-265/84013-02): QA program does not identify methods of accepting a procured item. The inspector reviewed revised procedures QP7.1, QP7.6, QP7.52 and QP4.1. These procedures require that each procured safety-related item have a
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Certificate of Compliance and a receipt inspection.
Source inspections l
are required for major procurement and when deemed necessary by CECO Quality Assurance. This item is closed.
l (Closed) Unresolved Item (50-254/84015-03; 50-265/84013-.03): Like for like items being procured as commercial grade. The inspector reviewed j
revised procurement procedures. The procedures require ASME III and
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safety-related items to be procurad as safety-related.
Provisions for j
CECu to assume 10 CFR 21 responsibility for items that must be procured
as commercial grade and dedicated to safety-related applications are included in the revised procedures. This item is considered to be closed.
I (Closed) Unresolvec Item (50-254/84015-08; 50-265/84013-08): MSIV spare discs procured with questiens pertaining to their fabrication. The inspector reviewed the revised purchase order for MSIV stems and discs.
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Tia original purchase' order did not include proper specification. The prxurement package with the revised purchase order included documented mill tests, certified material test reports, tensile tests, dimensions, radiographic and liquid penetrant examinations and receipt inspection documents..This item is closed.
i 3.
TI 2515/64R1 (Closed) TI 2515/91 (Closed)
a.
Equipment Classification The inspector selected six components in the reactor trip system and seven components in the low pressure injection / residual heat removal system for examination. The components selected were:
Low Pressure Injection / Residual Reactor Trip System Heat Removal System Scram Button Mode Switch Valve M0-1-1001-29B Pilot Valves Valve M0-1-1001-47 i
Hydraulic Pistons Valye M0-1-1001-78 Fuse Pressure Transmitter PT-1001-78 Auxiliary Trip Relays 103A, B, C, D Relief Valve RV-1-1001-125B Flow Element R0-1-1001-73C Pressure Switch PS-1-1053-F For the selected components, the inspector performed the following reviews:
(1) The inspector reviewed the Quad Cities safety-related component lists, controlled drawings, maintenance and test procedures, work requests, warehouse issue documents, quality assurance audits and surveillance and applicable modification packages.
All of the selected components were appropriately identified as safety-related..
(2) To determine the level of plant management oversight, the inspector reviewed procedures controlling the classification of structures, systems, components and parts; maintenance; modifications; procurement, storage and issue; inspection and testing of sefety-related items; quality assurance procedures, audits and surveillance; and corporate level procedures for
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activities impacting safety-related structures, systems and l
components.
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(3) The inspector reviewed Procedures QP12.1, " Classification and l
l Listing of Safety-Related Structures Systems and Components,"
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l QP2-53, " Operations-Classification of Structures, Systems and
L Components," and QP3-3, " Classification of Systems, Components, I
Parts and Material". These procedures provide direction for
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the performance of activities affecting safety-related structures, systems and components.
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(4) The inspector reviewed procedures for training and indoctrination of personnel performing activities affecting safety-related Items. Training und indoctrination records of persons whose names were selected from safety-related work reque ts indicated that each individual had received the necessary training to qualify him to work on the equipment covered by the work requests.
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(5) The inspector reviewed six audit reports and 46 surveillance reports documenting Quality Assurance Audits and Surveillance,
involving safety-related activities. The Quality Assurance organization maintains a schedule of planned audits and surveillance for safety-related activities at the plant.
(6) The corrective action program for safety-related activities is described in the licensee's Quality Assurance Manual.
The inspector's review of corrective action for audit and surveillance findings revealed that corrective action for these findings was timely and adequate. The Quality Assurance Department also schedules followup inspections of corrective actions after the action is complete and a finding is closed to determine if the corrective action was adequate to prevent a recurrence of the problem.
(7) Review and evaluation of information concerning malfunctioning of equipment is controlled by the licensee's nonconformance (NCR) and Deviation Report (DR) programs.
Both NCRs and DRs are reviewed by management, quality assurance, and' engineering, and when appropriate by the vendor or architect / engineer to determine the suitability of the equipment to perform its design function.
(8) The inspector reviewed four safety-related modifications on the RHR system. The modification packages, drawings, work requests, travelers and inspection reports were clearly identified as safety-related activities.
No violations or deviations were identified.
b.
Vendor Interface The inspector reviewed Procedures QP17-51, " Quality Assurance Records Per Operations - Control of Station Records," QP3-52,
" Design Control for Operations - Maintenance," and QAP-1800-9,
" Control of Vendor Equipment Technical Information." These procedures assure that vendor information for safety-related
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components is current and complete. Vendor manuals for six components in the reactor protection (trip) system were reviewed for completeness and to determine whether the manuals accurately reflected the installed equipment. Of the six components selected from the RHR system, controlled manuals were available for five components.
One component manual was missing at the time of
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inspection. The licensee immediately initiated action to locate the missing vendor manual and to procure another manual from the.
vendor.
The. inspector did not identify any installed components that had been supplied by a vendor who had gone out of business. Vendors for components selected for inspection are major suppliers to the nuclear industry. The licensee's procedures for controlling and l
replacing equipment and vendor technical information were reviewed and determined to be adequate to control situations where the vendor goes out of business, manuals are misplaced or the vendor refuses to supply information.
No violations or deviation were identified.
c.
Post Maintenance Testing
'The inspector selected three valves in the RHR system and one pump
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motor for review to verify that the licensee was implementing a post maintenance test program.
For the selected components, the inspector determined the following:
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(1) - Written post maintenance test procedures and checklists have been developed by the plant technical staff. The inspector reviewed procedures and completed tests to verify that post maintenance testing was being accomplished on the selected components in accordance with-licensee commitments.
(2) Criteria and responsibilities for maintenance approval and for
. designating activities as safety-related and non safety related have been established in work request procedures', and for the-inspection of post maintenance testing activities in both quality assurance procedures and plant administrative procedures.
(3) Methods fur performing functional testing following raaintenance q
for safety related components have been developed and are
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delineated in published technical staff procedures, operator l
surveillance procedures, preventive maintenance and quality l
control surveillance procedures.
(4) The inspector reviewed ten completed safety-related work requests and their supporting documentation.
The work requests were appropriately classified as safety-related activities, properly approved and the persons who performed the activity and inspections were identified on the work request and supporting documentation.
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l No violations or deviations were identified, j
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d.
Reactor Trip System Reliability.
At Quad Cities, on-line functional testing of the scram pilot-
solenoid valves is performed as reactor protection. system instrument channel functional tests at the frequency required by the Technical Specifications.
The inspector reviewed test procedures and test
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results for the following tests:
Reactor High Pressure Scram High Drywell Pressure Scram APRM Rod Block and Scram
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Low and Low-Low Water Level Trip i
Main Steam Line Isolation Main Steam Line High Radiation i
Low Condenser Vacuum Scram Turbine Control Valve Fast Closure Mode Switch on Shutdown Scram RPS Electrical Protection Assemblies Procedures were adequate and' test cata sheets indicated that the testing was being accomplished at the frequencies required by the
Technical Specifications.
No violations or deviations were identified.
4.
Exit Interview The inspector met with licensee representatives at the conclusion of the inspection and summarized the scope and findings of the inspection. The licensee acknowledged the inspector's comments. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed during the inspection. The licensee did not identify any such documents or processes as proprietary.
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