IR 05000327/1979064
| ML19211D239 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/27/1979 |
| From: | Cottle W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19211D238 | List: |
| References | |
| 50-327-79-64, NUDOCS 8001170239 | |
| Download: ML19211D239 (6) | |
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Report No. 50-327/79-64 Licensee: Tennessee Valley Authority 500A Chestnut Street
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Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant Docket No. 50-327 License No. CPPR-72 Inspection at Sequoyah Site Near Chattanooga, Tennessee Inspector:
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W. T. Cottld~
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H. C. Dance, Slction Chief, RONS Branch Date Sir,nea SUMMARY Inspection on October 1 - November 2, 1979 Areas Inspected This routine, unannounced inspection involved 78 inspector-hours onsite in the areas of plant tours, followup of previously identified items, followup of plant incidents, readiness of the facility for an operating license, and followup of IE Bulletins and Circulars.
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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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 Other licensee employees contacted included 4 shift engineers, 1 technician, 4 operators, 3 engineers, 2 security force members, and 15 corporate office personnel.
Other Organizations J. Martin, USNRC G. Gibson, USNRC G. Belisle, USNRC M. Gouge, USNRC T. Donat, USNRC R. Trojanowski, USNRC L. Modenos, USNRC G. Miller, USNRC L. Jackson, USNRC T. Gibbons, USNRC K. Besecker, USNRC A. Tillman, USNRC J. Wray, USNRC G. Troup, USNRC H. Dance, USNRC C. Stahle, USNRC S. Butler, USNRC T. Borst, Battelle Labs W. Hatch, Los Alamos Scientific Labs 2.
Exit Interview The inspection scope and findings were summarized with the plant superintendent and members of his staff on October 2,12,19 and November 2, 1979.
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3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Readines of the Facility for Receipt of an Operating License The inspector 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.
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 condi-tions regarding open times were consistent with those recommended by the inspector.
The inspector also discussed the basis utilized for determina-tion of the completion categorization of individual open items with licensee representatives.
The inspector participated in a meeting with NRC and TVA representatives on October 31 during which the status of each item identified as having a potential impact on Unit 1 licensing was discussed.
No items of noncompliance or deviations were identified.
6.
Plant Tours The inspector toured various areas of Unit 1 on October 3, 5, 10, 19, 22, 29 and November 1, 1979.
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:
a.
Housekeeping practices b.
Protection of installed instrumentation.
Inplace storage of permanent plant equipment.
c.
d.
Ability to hear PA system announcements in plant areas.
e.
Fire prevention / protection measures for hot work.
f.
Posting of hold tags, caution tags and alteration tags.
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Measures to exclude foreign materials from entry into clean system.
h.
Unit operator and shift engineer log books.
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Condition of ins'slled fire protection equipment.
j.
General shift operating practices.
k.
Access control for the Unit 1 protected area and fuel storage area.
No items of noncompliance or deviations were identified.
7.
Followup of Previously Identified Items (Closed) Open Item (327/79-07-03) Technical Specifications did not address the 125 VDC systems for the emergency diesel generators. The inspector reviewed specifications and found that appropriate limiting conditions for operation and surveillance requirements for the 125 VDC systems were included in the revision dated September 1, 1979. The inspector had no further questions in this area.
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(Closed) Open Item (327/79-39-02) Steam generator chemical feed lines. The inspector verified that the chemical feed lines for steam generators 2 and 3 were installed per the applicable FSAR drawing (Figure 10.4-19).
The inspector had no further questions in this area.
(Closed) Licensee Identified Item (327/79-43-02 and 328/72-24-02)
Environmental qualification of containment hydrogen monitoring panels. The inspector reviewed licensee's final report on NCR EEB 79-10 and the certi-fication of modifications and retesting performed by the vendor to ensure that the equipment met all purchase specifications. The inspector had no further questions in this area.
(Closed) Open Item (327/78-39-05) Inconsistency of QA audit frequencies.
The inspector reviewed Section 17.2.18 and Table 17.2-7 of Topical Report TVA-TR75-1A, revision 3, and verified that the inconsistency had been resolved. The inspector had no further questions in this area.
(Closed) Open Item (327/78-39-44) Record keeping inadequacies-Radiological Hygiene Branch.
The inspector reviewed Revision 0 of Quality Assurance Procedure 6.1, " Retaining and Storing Quality Assurance Records". The inspector discussed the adequacy of the procedure with the Region II QA Audit Team Leader and had no further questions in this area.
(Closed) Open Item (327/79-19-05) Application of temperature corrections to functional test data on hydraulic shock suppressors. The inspector reviewed licensee correspondence which specified the maximum service temperatures for hydraulic shock suppressors and licensee's maintenance instruction (SQNP/MI-6.13B) which established the acceptance criteria for lockup and bleed rates utilized during functional testing. The combinations of allow-able service temperatures, lockup and bleed rates were then compared with
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Appendix C of NUREG 0467 (June 1978) and found to be within the established limits. The inspector had no further questions in this area.
(0 pen) Licensee Identified Items (327/79-46-02 and 327/79-46-03) Violation of heatup and cooldown rate limits on reactor coolant system and pressurizer.
The inspector reviewed licensee's interim report on NCR 12P/13P and a memorandum from the NSSS vendor which concluded that safe operation of Unit I would not be jeopardized. The inspector concurs that the final evaluation of the incidents is not a prerequisite for issuance of an operating license or for initial operation of Unit 1; however, these items will remain open pending review and approval of licensee's final report on NCR 12P/13P.
(0 pen) Open Item (327/78-39-14) Housekeeping program for maintenance activities.
The inspector reviewed a proposed change to the Operations Quality Assurance Manual in response to this item.
The change was not adequate in that it did not establish a housekeeping program for maintenance activities as required by licensee's commitment to ANSI N45.2.3-1973.
This item remains open.
8.
Followup of Plant Incidents The inspector reviewed the circumstances involving a fire in the Auxiliary Building 480V Common Board on October 2.
An inspection of the switchgear revealed no apparent reason for the fire. The 480V Common Board is located on elevation 749 of the Control Building and supplies non-safety related loads. Damage from the fire was minimal. The response of the plant fire brigade and the investigation conducted by the licensee appeared to be adequate.
The inspector reviewed the circumstances involving an apparent breach of physical security procedures which occurred on October 14.
The incident involved an individual being admitted to the protected area without being subjectea to a search of hand-carried packages. The inspector reviewed the licensee's investigation reports and the corrective actions taken to prevent reoccurrence and had no further questions.
No items of noncompliance or deviations were identified.
9.
Followup of IE Bulletins, Circulars and Notices The inspector verified that the following Information Notices had been received at the facility and routed to the apprcpriate levels of supervision:
IN 79-01 IN 79-10 IN 79-20 IN 79-02 IN 79-11 IN 79-21
IN 79-03 IN 79-12 IN 79-04 IN 79-13 IN 79-05 IN 79-14 IN 79-06 IN 79-15 IN 79-07 IN 79-16 IN 79-08 IN 79-17 1762 077
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-5-o The inspector verified that the following IE Circulars had been received at the facility, routed to the appropriate levels of supervision, and that corrective action had been initiated when appropriate:
IEC 78-07 IEC 79-04 IEC 79-13 IEC 78-08 IEC 79-05 IEC 79-14 IEC 78-13 IEC 79-08 IEC 79-16 IEC 78-15 IEC 79-11 IEC 79-17 IEC 78-16 IEC 79-12 IEC 79-18 The inspector completed the review of licensee's response to IEB 79-13 (Revision 1).
The review included a verification of the final disposition of the surface irregularities noted on weld number IFD 00131--1 in a pre-vious inspection. This item is closed.
10.
Independent Inspection Effort The inspector routinely attended the morning scheduling and staff meetings during the reporting period. Thase meetings provide a daily status report on the construction and testing activities in progress as well as a discus-sion of significant problems or incidents associated with the construction, preoperational testing, and operations effort.
The inspector reviewed licensee's proposed schedule of surveillance testing on the solid state protection system and the general scope of the proposed tests and found them to be consistent with the Technial Specification surveillance requirements.
The inspector participated in the Emergency Planning Review Meetings con-ducted by personnel from the office of Nuclear Reactor Regulation on October 15 and 16.
The meetings were held at the plant site and the Chattanooga YMCA.
The inspector reviewed the Unit 2 Special Nuclear Material (Part 70)
license provisions prior to licensee receiving the first shipment of Unit 2 fuel assemblies on October 13.
The inspector verified the physical security requirements of the Part 70 license in discussions with personnel from the Fuel Cycle and Materials Safety Division prior to the first shipment.
The inspector participated in the Radiological Emergency Plan drill conducted on October 28 and 29.
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.
No items of noncompliance or deviations were identified.
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