IR 05000254/1979013
| ML19208A324 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/13/1979 |
| From: | Chrissotimos N, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19208A318 | List: |
| References | |
| 50-254-79-13, 50-265-79-11, NUDOCS 7909130378 | |
| Download: ML19208A324 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-254/79-13; 50-265/79-11 Docket No. 50-254, 50-265 License No. DPR-29, DPR-30 Licensee:
Commonwealth Edison Company
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Post Office Box 767 Chicago, Illinois 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 and 2 Inspection At: Quad-Cities Site, Cordova, IL Inspection Conducted: May 29-Jite 27, 1979
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/ I N. J. Chrissotimos p 7//3/77 Inspector:
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Approved By:
R. L. Spessard, Chief 7 /13!7'l Reactor Projects Section 1 Inspection Summary Inspection on May 29-June 27, 1979 (Report No. 50-254/79-13; 50-265/79-11)
Areas Inspected: Routine, announced resident inspection of maintenance, plant operations, physical protection - security organization, physicsl protection physical barriers, physical protection - access control (identification, authorization, badging, search, and escorting), physical protection - communications, review and followup on licensee event reports, calibration of safety-related components required by Technical Specifi-cations and those not required by Technical Specifications, surveillance, fire protection, followup on Headquarter requests, review and audit, surveillance of core power limits / thermal power evaluation, radiation protection, radioactive waste systems and followup on information letter.
The inspection involved 185 inspector-hours onsite by one NRC inspector.
Results: Of the 17 arcas inspected, no apparent items of nooo@?iance were identified in 16 areas; one apparent item of noncomplie (L4ficiency -
Failure to log equipment status - Paragraph 7) was ident%i 2.1 ace area.
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DETAILS 1.
Persons Contacted
- N. Kalivianakis, Superintendent J. Gudac, Assistant Superintendent
- T. Tamlyn, Lead Operating Engineer
- K.
Graesser, Administrative Assistant L. Gerner, Technical Staff Supervisor D. Bax, Operating Engineer, Unit 2
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G. Conschack, Operating Engineer, Unit 1 R. Spear, Maintenance Engineer J. Heilman, Quality Assurance, Operations The inspector also interviewed several other licensee employees, including shift engineers and foreman, reactor operators, technical staff p-rsonnel and quality control personnel.
- Denotes those present at the exit interview on June 27, 1979.
2.
Maintenance The inspector, through direct observation and record review verified that reactivity control, instrumentation, and containment cooling systems maintenance activities were conducted in accordance with established procecures and Technical Specifications; verified that required administrative approvals were obtained prior to initiating work; verified that maintenance activities were accomplished using approved and technically adequate procedures; verified that the activities were inspected in accordance with the provisions of licensee's requirements; verified that activities included func-tional testing and calibration as necessary prior to returning the component or system to an operating status; verified that quality control records were available; verified that activities were accomplished by qualified personnel; verified that radiological controls were established for worker protection, including mini-mizing personnel exposure; verified that materials or components used were certified as required by plant procedures; verified that QC hold points, plant status and safety controls, and tsgging operations appeared adeouate; and verified that associated limiting conditions for operation were met in accordance with Technical Specifications.
The following maintenance activities in progress were observed:
Rebuilding of CRD 111 Valve (Unit 1)
IRM Preamplifier Instrument Maintenance (Unit 1)
Control Rod Blade Guide Handle Repairs (Units 1 and 2)
RHR Service Water Pump Overhaul (Units 1 and 2)
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The following completed maintenance package was reviewed:
Rebuilding of CRD 111 Valve (Unit 1)
No items of noncompliance were identified.
3.
Physical Protection - Security Organization The inspector verified by observation and personal interview (once during each operating shift) that at least one full time member of the security organization who has the suthority to direct the physical security activities of the security organization was onsite at all times; verified by observation that the security organization was properly manned for all shifts; and verified by observation that
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members of the security organization were capable of performing their assigned tasks.
The inspector also observed weapon quali-fications conducted by contract security personnel during the month.
No items of noncompliance were identified.
4.
Physical Protection - Physical Barriers The inspector verified that certain aspects of the physical barriers and isolation zones conform to regulatory requirements and commit-ments in the physical security plan (PSP); that gates in the protected area were closed and locked if not attended; and that isolation zones were free of visual obstructions and objects that could aid an intruder in penetrating the protected area.
No items of noncompliance were identified.
5.
Physical Protection - Access Control (Identification, Authorization, Badgir.g, Search and Escorting)
The inspector verified that all persons and packages were identified and authorization checked prior to entry into the protected area (PA), all vehicles were properly authorized prior to entry into a PA, all persons authorized in the PA were issued and displayed identification badges, records of access authorized conformed to the PSP, and all personnel in vital areas were authorized access; verified that all persons, packages, and vehicles were searched in accordance with regulatory requirements, the PSP, and security procedures; verified that persons authorized escorted access were accompanied by an escort when within a PA or vital area; verified that vehicles authorized escorted access were accompanied by an escort when within the PA; and verified by review of the licensee's authorization document that the escort observed above was authorized to perform the escort function.
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No items of noncompliance were identified.
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6.
Physical Protection - Communicatious The inspector verified by observation (during each operating shift)
that communications checks were conducted satisfactorily at the beginning of and at other prescribed time (s) during the security personnel work shift and that all fixed and roving posts, and each member of the response team successfully communicated from their remote location; and verified that equipment was operated consistent with requirements in the PSP and security procedures.
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No items of noncompliance were identified.
7.
Plant Operations The inspector reviewed the plant operations, including examinations of control room log books, routine patrol sheets, shift engineer log book, equipment outage logs, special operating orders, and jumper and tagout logs for the month of June, 1979.
The inspector also made visual observations of the routine surveillance and functional tests in progress during the period. This review was conducted to verify that facility operations were in conformance with the require-ments established under Technical Specifications, 10 CFR, and Administrative Procedures. A review of the licensee's deviation reports for the period was conducted to verify that no violations of the licensee's Technical Specifications were made. The inspector conducted tours of Units 1 and 2 reactor buildings and turbine buildings throughout the period and noted that the monitoring instru-mentation was recorded as required, radiation controls were properly established, fluid leads and pipe vibrations were minimal, seismic restraint oil levels appeared adequate, equipment caution and hold cards agreed with control room records, plant housekeeping conditions /
cleanliness were adequate, and fire hazards were minimal. The inspector observed shift turnovers to verify that plant and component status and problem areas were being turned over to relieving shift personnel. The inspector observed sampling and chemical analysis of water chemistry samples to verify that water chemistry was being maintained in accordance with Technical S;mcifications.
On June 13, 1979 while observing shif t turnover in the control room, the inspector noted that Intermediate Range Monitor Channel 17 was bypassed. The unit was in the run mode, and bypassing of an IRM channel is permissible and does not affect safe unit operation.
Uptn reading the log book entries and inquiring with the unit operator and shift engineer, no apparent reason for the bypass position was provided. This is contrary to operating log and shift turnover procederes and is an item of noncompliance with Technical Specifi-cation 6.2.A.
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Prior to the conclusion of the inspection, this condition was entered into the operating log and an operating order was issued reinforcing adherence to shift changeover and log book entry pro-cedures. Corrective and preventive actions have been taken and, therefore, no response to this noncompliance is required.
During the review of the licensee's deviation reports, the inspector found three deviations involving promotions. The persons involved meet the requirements of Technicians as per American National Standard 18.1, 1971, but do not meet the requirements of a Repairman which appears to be a less stringent requirement.
The persons involved were promoted to repairman. The inspector informed the l'icensee that a clarification of the standard is needed and that this is an open item that will be followed up during subsequent inspections.
(254/79-13-01; 265/79-11-01)
Except as previously described, no items of noncompliance were identified.
8.
Review and Audit On May 23, 1979, the inspector observed a Technical Specification change committee meeting.
The inspector verified that provisions of Technical Specifications dealing with membership, review process, and qualifications were met.
The inspector also verified that decisions made were reflected in the meeting minutes and that correc-tive actions proposed were taken.
No items of noncompliance were identified.
9.
Review of Units 1 and 2 Surveillance The iaspector reviewed the surveillance program to determine whether the surveillance of components or equipment associated with safety-related systems is being conducted as required by Technical Specifi-cations and in accordance with procedures.
The review consisted of verifying that each surveillance test was accomplished in accordance with properly approved procedures and the procedures included prerequisities, functional tests, acceptance criteria, and operational checks prior to returning the equipment to service. The inspector examined the procedure's technical content and the test results to determine conformance with the Technical Specification requirements. The inspector also examined personnel qualifications of those who conducted surveillances.
Specific details of this review have been documented and reported in Inspection Reports 50-254/79-12; 50-265/79-10.
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No items of noncompliance were identifieo.
10.
Review of Units 1 and 2 Calibrations The inspector reviewed the licensee's program for Units 1 and 2 calibrations to determine whether the calibration of components and equipment associated with safety-related systems and/or functions both, identified and not identified, in the Technical Specifications as requiring calibration at a specific frequency are calibrated.
The review consisted of verifying the f requency of calibration, acceptance values, detailed stepwise instructions and review of procedures used to calibrate the components. The technica'l content and component trip points were adequate. The inspector also veri-fied that calibration standards being used are traceable to independent testing organizations.
The following calibration records for March, April and May 1979 were reviewed:
APRM Rod Block and Scram Calibration Reactor High Pressure QIS 551 High Drywell Pressure QIS 751 RHR Containment Spray Permissive Reactor Low Pressure Switch Calibration Core Spray Pump Discharge Pressure SRM Rod Block QIS 151 Containment Pressure QIS 30-51 SPLC Level Transmitter 1153 RCIC Flow Indicator 1340 SBGT Temperature Indicator 7541 The following test equipment was verified for proper calibration and traceability:
Pressure Test Gauge 49 Pulse Generator 188 Digital Meter 122 The inspector also witnessed the following calibrations:
RHR Pressure Transmitters 1043A and 1044A Functional checks of ADS instrumentation No items of noncompliance were identified.
11.
Site Review of Licensee Event Reports Licensee event reports were reviewed to verify that details were accurately reported; that the cause was identified; that the event-6-1 ' tj
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was reviewed and evaluated in accordance with technical specifications; and that the corrective action was taken as described in the report.
1he following LER's were reviewed:
Unit 1 R0-79-19/03L, dated May 24, 1979, " Vacuum Breaker Failed To Give Closed Indication."
Unit 2
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R0-79-10/03L, dated May 14, 1979, " Fuel Pool Radiation Mon'itor Failed Upscale."
R0-79-11/03L, dated May 21, 1979, " Cable Pan Incorrect Feed."
The inspector verified that no equipment needed for safe shutdown of the plant is fed from this motor control center.
Also, the licensee has investigated the unit's redundant motor control center and the two similar motor control centers on Unit I and determined that no cable errors exist in those cable trays. The licensee plans to submit an oc$ated LER to reflect these actions.
No items of noncompliance were identified.
12.
Surveillance of Core Power Limits / Thermal Power Evaluation During the months of April, May and June 1979, the inspector verified that linear heat generation rates; core maximum peaking factors; minimum critical power ratios and the limiting average planar heat generation rates were all within the requirements of Technical Specifications. The inspector also reviewed the results of the core thermal power evaluation.
No items of noncompliance were identified.
13.
Radiation Protection The inspector teviewed special work permits and verified through observation that the requirements we e being followed for SWP 747-49 and SWP 771-79 Cleanup Pump Maintenance and SWP 768-79 Torus Hanger Inspection.
No items of noncompliance were identified.
14.
Radioactive Waste Systems During the week of June 4 to June 8, 1979, the inspector verified that required sampling prior to a water discharge was completed in-7-
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accordance with established procedures, that effluent monitors were operable and tl.-t approvals were obtained prior to the release.
No items of noncompliance were identified.
15.
Followup on Headquarters Requests Temporary Instruction 2515/22 identifies problems with terry a.
turbines equipped with PG-PL Woodward Governors. The inspector verified that the licensee's terry turbines do not incorporate these type of governors.
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Temporary Instruction 2515/20, " Review Licensee Actions in Response to IE Bulletin 7814." The inspector verified that the licensee has implemented a program to replace the Buna-N material on a schedule such that the total time in service will not exceed the end of service life of the material.
"BWR Offgas System Operations." The in'spector verified the c.
understandings of the telephone conversations held between the licensee and h7C.
Plant procedures were modified to reflect the commitment made and the modification of the rupture discs have been sent to the licensee's engineering department.
Reference: Letter from T. A. Ippolito (NRR) to C. Reed (Ceco)
dated April 16, 1979.
No items of noncompliance were identified.
16.
Fire Protection The inspector verified that hydrants have 2 1/2" gate valves ou unused ports, that yard hydrant HC-1 has been modified to allow 360 degree revolution of the stem and that barricades are provided for hydrants. These findings are in accordance with items 50, 52 and 53 of Fire Protection Evaluation "NRC Staff Positions."
17.
Electro-Motive Information Letter Electro-motive provided information to the licensee on por sible damage to turbocharger bearings on diesel generators, under certain operating conditions. The inspector verified that the conditions described as possible causes have not occurred and that operating procedures do not reflect operation that would enhance this condition.
The licensee's evaluation of this information concluded that the matter was not a reportable event. The inspector concurred with the licensee's evaluation.
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No items of noncompliance were identified.
18.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 27, 1979 and summarized the scope and findings of the inspection activities.
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