IR 05000328/1981007
| ML19343D529 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/16/1981 |
| From: | Skinner P, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19343D528 | List: |
| References | |
| 50-328-81-07, 50-328-81-7, NUDOCS 8105050153 | |
| Download: ML19343D529 (4) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
E REGION 11 101 MARIETT A ST., N.W., SulTE 3100
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ATLANTA, GEORGIA 30303
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Report No. 50-328/81-07 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah 2 Docket No. 50-328
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License No. CPPR-73 Inspection at Seq oyah site n r Chattanooga, Tennessee Inspector:
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Date Signed P. H. Skinner /
Approved by:
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C.M.1prfght, K ion ief,
/Date/ Signed
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Engineering Insp cti ranch Engineering an' Techn cal Inspection Division SUMMARY Inspected on March 3-6, 1981 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours on site in the areas of plant procedures (operating, maintenance and emergency).
Results Of the areas inspected, no violations or deviations were identified.
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t REPORT DETAILS 1.
Persons Contacted Licensee Employees
- W. T. Cottle, Assistant Plant Superintendent
- J. M. McGriff, Assistant Plant Superintendent
- W. J. Glasser, Power QA/AS Coordinator
- L. D. McCloud, QA Supervi'sor
J. W. Doty, Maintenance Supervisor (M)
B. M. Patterson, Maintenance Supervisor (I)
D. J. Record, Operations Supervisor Other licensee employee' included office personnel.
s NRC Resident Inspector
- S. Butler
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- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on March 6,1981 with those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are. acceptable or may involve violations or devia-tions. An unresolved item identified during this inspection is discussed in paragraph 5.c.
5.
Plant Procedures (42400, 42450, 42451, 42452)
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References:
(1)
ANSI N18.7-1976, Administrative Controls and
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Quality Assurance for the Operational Phase of
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Nuclear Power Plants l
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Regulatory Guide 1.33, Quality Assuran:e Program
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Requirements (Operation), Revision 2 February 1978 l
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(3)
N-0QAM, Part II Section 1.1, Plant Operating Instructions dated November 10, 1980 b.
Review of Procedures The inspector conducted a r. view of selected plant procedures in accordance with references (1) through (3) above to determine that procedures already in use at the operating facility are revised, where applicable, to reflect the new facility; to determine that procedures.
are modified as required to specify differences in system build between systems using the same procedure; to determine that separate proce-dures, where necessary, are available to operate systems that are significantly different in design to those of the lead facility; and to verify that responsibilities have been assigned to assure that the procedures will be reviewed, updated, and approved as required. The procedures selected were in the areas of administration, general operating, system operating, surveillance, maintenance, abnormal,
emergency, and security procedures. The procedures selected for review are listed below:
AI-4, Plant Instructions - Document Control, Revision 30 dated 1/2/81 AI-5, Shift and Relief Turnover, Revision 8 dated 9/12/80 SI-105, Vital Battery Bank and Charger Performance Tests, Revision 5 dated 12/22/80 SI-111, Testing and Setting of Main Steam Safety Valves, Revision 4 dated 11/26/79 SQM-1, Sequoyah Nuclear Plant Maintenance Program, Dated 12/13/79 SOI-1.1, Main Steam Supply, Revision 6 dated 6/16/80 SOI-62.4, CVCS Purification Systems, Revision 7 dated 6/24/80
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GOI-2, Plant Startup From Hot Standby to Minimum Load, Revision 15 dated 1/13/81 G0I-5, Normal Power Operation, Revision 9 dated 2/5/81 A0I-3, Small Reactor Coolant System Leak, Revision 9 dated 12/23/od A0I-8, Tornado Watch, Revision 5 dated 1/5/81 A0I-21.1, Loss of 125V DC Vital Battery Board I, Unit 1, Revision 5 dated 9/17/80 i
A0I-21.5, Loss of 125V DC Vital Battery Board I, Unit 2, Revision 2 dated 12/17/80
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E0I-4, Emergency Boration, Revision 7 dated 12/24/80
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E0I-7, Control Room Inaccessibility, Revision 10 dated 2/5/81
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PHYSI-13H, Unit 2, Reactor Coolant. Pump Mctors Prefire Plan, Revision 1 dated 7/29/80
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Review of Procedure Format N0QAM, Part II Section 1.1, dated 11/10/80 provides the general format to be considered in the preparation and review of each type instruction with the exception of Emergency Operating Instructions. During the review of the various procedures identified above, none of the proce-dures reviewed used the format specified.
Since this procedure (Section 1.1) has recently been revised (November 1980) to specify this format, the inspector will review procedures on subsequent inspections to determine if this commitment is being met. This is an unresolved item (328/81-07-01).
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