IR 05000327/1979073
| ML19305C682 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/05/1980 |
| From: | Cottle W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305C679 | List: |
| References | |
| 50-327-79-73, NUDOCS 8003310257 | |
| Download: ML19305C682 (8) | |
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UNITED STATES
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O, 101 MARIETTA ST., N.W., SulTE 3100
\\.....o ATLANTA, GEORGIA 30303
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Report No. 50-327/79-73
. Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant Docket No. 50-327 License No. CPPR-72
Inspection at Sequoyah site near Chattanooga, Tennessee M.h Tahw 8:
.Q /9 Vo Inspe or:
g7T.Cottle, Date Signed
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'2.5 ((O Approved by: i H. C. Dance, Section Chief, RONS Branch D/te Signed SUMMARY Inspection on December 1-31, 1979 Areas Inspected
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This routine, unannounced inspection involved 59 inspector-hours on site in the areas of plant tours, followup of previously identified items, follovup of plant
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incidents, readiness of the facility for an operating license, and followup of
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previously identified enforcement matters.
Results Of the areas inspected, no apparent items of noncompliance or deviations were
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identified.
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A DETAILS 1.
Persons Contacted Licensee Employees
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J. M. Ballentine, Plant Superintendent C. E. Cantrell, Assistant Plant Superintendent W. F. Popp, Assistant Plant Superintendent W. E. Andrews, Quality Assurance Supervisor W. M. Quinn, Operations Supervisor R. S. Kaplan, Captain, Public Safety Services W. H. Kinsey, Results Supervisor R. J. Kitts, Health Physics Supervisor
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J. T. Crittenden, Captain, Public Safety Services D. J. Record, Assistant Operation Supervisor J. W. Doty, Maintenance Supervisor (M)
J. M. McGriff, Maintenance Supervisor (I)
W. A. Watson, Maintenance Supervisor (E)
E. A. Condon, Preoperational Test Supervisor C. R. Brimer, Outage Director R. H. Ector, Assistant Outage Director Other licensee employees contacted included three shift engineers, two technicians, four operators, five engineers, two security force members, seven corporate office personnel, and five construction craftsmen.
Other Organizations J. Ahearne, USNRC
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G. Sauter, USNRC
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A. Belisle, USNRC J. Mcdonald, USNRC M. Gouge, USNRC H. Asher, USNRC L. Modenos, USNRC 2.
Exit Interview The inspection scope and findings were summarized with the plant superintendent and members of his staff on December 6, 17, and 21, 1979.
3.
Licensee Action on Previous Inspection Findings (Closed) Infraction (327/79-46-01) Failure to control a temporary altera-tion to a safety related component. The inspector reviewed the licensee's corrective actions and had no further questiqn,s, The inspector did discuss the necessity of licensee's responses to items of noncompliance addressing both the detailed steps taken for the specific item and the steps taken to
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i prevent recurrence of a generic nature. Licensee management acknowledged
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the need to include such information in the written responses to items of noncompliance.
4.
Unresolved Itecs Unresolved items were not identified during this inspection.
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5.
Readiness of the Facility for Receipt of an Operating License The inspec'.or continued to track the status of those items identified as having a potential impact on the issuance of an operating license for Unit 1.
Areas addressed included inspector identified items, construction deficiency reports, construction status, preoperational testing status, and operational preparedness.
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Throughout the inspection period, the listing of open items was discussed with licensee management representatives on a continuing basis.
Licensee management was encouraged to assure that their requests for license
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conditions regarding open items were consistent with those recommended by the inspector. The inspector also discussed the basis utilized for deter-mination of the completion categorization of individual open items with licensee representatives.
The inspector attended an Advisory Committee on Reactor Safeguards (ACRS)
subcommittee meeting in Washington, D. C. on December 4 and a full ACRS meeting on December 7, 1979. The subject of bothmeetings was the readiness of Sequoyah Unit 1 to receive a low power operating license. As a result of the meeting on December 7, the ACRS issued a letter on December 11, 1979, recommending that a low power operating license be issued for Sequoyah Unit 1.
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s During this reporting period, the inspector prepared an updated status report on those items identified as potentially affecting the issuance of an operating license and an open item report for inclusion in the Safety Evaluation Report. These reports were forwarded to Region II management on December 13 and 12 respectively.
No items of noncompliance or deviations were identified.
6.
Plant Tours
l The inspector toured various areas of Unit I on December 2, 10, 11, 12, 18, l
21, and 31.
The tours were conducted such that all accessible plant areas were inspected at least once during this reporting period. The following activities were observed / reviewed:
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a.
Housekeeping practices
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Prc xetion of installed instrumentation.
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Inplace storage of permanent plant equipment.
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Ability to hear PA cystem announcements in plant areas.
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Fire protection measures for hot work.
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Posting of hold tags, caution tags and alteration tags.
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Measures to exclude foreign materials from entry into clean system.
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Unit operator and shift engineer log books.
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Condition of installed fire protection equipment.
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General shift operating practices.
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Access control for the Unit 1 protected area and fuel storage area.
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No items of noncompliance or deviations were identified.
7.
Followup of Previously Identified Items a.
(Closed) Open Item (327/78-39-08) Definition of division of authorities and responsibilities for QAAS participation in joint audits. The inspector reviewed Revision 0 of ID-QAP 18.2 " Joint Quality Assurance Audits". This procedure defines the authorities and responsibilites of the respective audit staffs including reports, inputs and control of corrective actions, and provisions for NSRB review. This item is closed.
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b.
(Closed) Open Item (327/78-39-11) Definition of responsibility for audit of design activities during modifications performed at operating nuclear facilities. Revision 0 of ID-QAP 18.2 requires that joint quality assurance audits be conducted in the area of design modifica-tions.
In addition, provisions are made for rhe audit reports and e
subsequent correspondence on corrective actions to be forwarded to the NSRB.
L This item is closed.
c.
(Closed) Licensee Identified Item (327/79-36-01) Incorrect Velan Valve weights. The licensee has submitted the final report on this construc-tion deficiency in conjunction with the response to IEB 79-04.
The bulletin response is currently under evaluation by-the Office,of Inspection and Enforcement, Region II.
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This item is closed.
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d.
(Closed) Open Item (327/79-46-04) Receipt of U 235 incore flux detectors.
The inspector reviewed a memorandum from Westinghouse Electric Corpora-tion dated November 26, 1979 which certified that the U 235 content of each detector was.0041 grams. The inspector verified there was no
problem with the 0.99 gram limit on U 235 specified in the 10 CFR 30 Byproduct Material License.
This item is closed.
e.
(Closed) Licensee Identified Item (327/78-38-06) ERCW flow maldistri-bution to component cooling water heat exchangers. The inspector reviewed the proposed interim action to allow Unit 1 operation pending a final design resolution and found it to be acceptable. The inspector reviewed Revision 4 of SOI-67.1 (Valve checklist 67.1-1) and verified that the specified valve lineup had been incorporated into the procedure.
In addition, the inspector requested that an appropriate caution order be implemented to insure that the valve lineup would not be altered g
without the approval of the shift engineer. A caution order has been so implemented. This item is closed for Unit 1 but will continue to r
be followed for Unit 2 since a design change will be required prior to Unit 2 operation (328/78-27-07).
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(0 pen) LicenseeIdentified Item (327/79-36-08) Inadequate lubrication for emergency diesel generator turbocharger thrust bearings. The inspector discussed the results of the inspections conducted by the licensee and the diesel vendor on the turbo-charger units on each diesel generator. No significant wear was observed on any of the turbo charger thrust bearings.
In addition, the inspector reviewed the precautions incorporated into Revision 7 of SOI 82.lB, 82.2B, 82.3B and 82.4B to prevent routine hot restarts of the diesel generator units. The precautions appeared to be adequate to prevent damage to the turbo charger units. This item will remain open pending completion of licensee's design review and any subsequent modifications to the diesel generator lubricating oil systems.
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(Closed) Open Item (327/79-71-01) Unauthorized individual reversed I
indicator lamp lenses on a vital instrument inverter. The inspector reviewed the investigation conducted by the licensee and the resulting l
personnel actions. The inspector had no further questions in this
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area.
This item is closed.
h.
(Closed) Licensee Identified Item (327/79-36-16) Valve position indi-l cation transformers. The inspector reviewed Special Maintenance Instruction SMI-0-200-1 " status monitoring system Crydon Relay Burn-In" dated October 18, 1979. This procedure' required a 96-hour burn-in of all Crydon relays used in the status monitoring system. Discussions l
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with the Maintenance Supervision-Electrical revealed that all Unit I relays and the spare relays in power stores had been processed per the SMI.
This item, reported as NCR 700/714 is closed for Unit 1.
8.
Followup of Plant Incidents During the course of the reporting period, the inspector conducted followup activities on the following plant incidents:
a.
Injury to construction craftsman involved in fall from Unit 2 turbine casing on December 5,1979.
b.
Apparent falsification of a shift operating record discovered og December 7, 1979.
c.
Spiking observed on radiation monitoring channels on December 12 and 15, 1979.
(Spiking was later determined to be noise pickup from TIG l
Welding on a containment spray heat exhanger).
d.
Electrical fire on roof of service building on December 19, 1979.
The inspector reviewed the circumstances involved in each incident and, where appropriate, reviewed the actions taken by licensee management in response to the incident. Licensee's management response appeared to be both timely and adequate in each instance reviewed by the inspector.
No items of noncompliance or deviations were identified.
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9.
Independent Inspection Effort
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The inspector routinely attended the morning scheduling and staff meetings during the reporting period. These meetings provide a daily status report on the construction and testing activities in progress as well as a discussion of significant problems or incidents associated with the construction, preoperational testing, and operations effort.
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The inspector conducted a.walkdown of the auxiliary building gas treatment and the emergency gas treatment systems on December 2.
No discrepancies were noted which were not already being tracked on licensee's incomplete work punch lists.
The inspector reviewed licensee's response to IE Information Notice 79-22
" Qualification of Control Systems". The inspector had no comments on the response which was provided by the licensee per a request from the Office of Nuclear Reactor Regulation.
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-la-The inspector reviewed the revision to the Operational Quality Assurance Manual Part III Section 7.3 " Common-Mode Failures, Maintenance-Initiated"
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dated October 1, 1979. This revision requires that two fully qualified instrument mechanics be assigned to calibrate each safety-related instrument.
It also requires that the as-left calibration of the instrument be checked twice with the instrument mechanics exchanging functions after the first check. This requirement is implemented by Instrument Maintenance Section Instruction Letter IMS 1-9 for the Sequoyah Unit I facility.
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The inspector provided information concerning the P-250 plant computer (manufacturer, model number, number and type of inputs) in response to a request from the Region II office.
The inspector toured the Unit 1 facility with the Chairman, USNRC, and his technical assistant on December 11.
The inspector reviewed certain design provisions of the Sequoyah facility in response to a request from the Region II office concerning potential design problems identified by t,he Watts Bar Resident Inspector. The results of the review were transmitted to the Region II office on December 12.
The inspector observed maintenance activities involving staking of the tube
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bundles on the IB containment spray heat exchanger on December 18.
The work in progress was discussed with the craf tsmen performing the staking.
The inspector discussed the controls required for designated vehicles and the criteria for including vehicles on the designated vehicle list with licensee management representatives on December 12 and 18.
The inspector met with licensee management representatives on December 19 to review the formal responsibilites and authority of the on site Quality
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Assurance Coordinator.
The inspector reviewed the planning activities and discussed the radiologi-f cal controls to be placed in effect for the installation of the Unit 1 primary source rods with the Station Health Physicist. The inspector conducted a back shif t inspection to witness preparations for the instal-lation of the source rods on December 18.
The inspector coordinated the effort to have dedicated phone lines installed
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in the Sequoyah Training Center PWR simulator room to support the conduct of NRC drills scheduled for January.
The inspector participated in discussions with TVA and NRR representatives concerning auxiliary building secondary containment and the proposed low power test program on December 21.
The inspector observed the personnel access control measures in effect on December 27 and 31.
Comments on improving the control afforded the picture-type identification badges were given to the, supervisor - Public Safety Services.
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o-7-o The inspector conducted a detailed review of Administrative Instructions 2-18 for inspector familiarity.
The inspector provided assistance to and coordinated the inspection activities of those NRC personnel listed in Section 1 during their visits to the facility in this reporting period.
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No items of noncompliance or deviations were identified.
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