IR 05000327/1979049
| ML19260A668 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/10/1979 |
| From: | Burnett P, Donat T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260A665 | List: |
| References | |
| 50-327-79-49, NUDOCS 7912030065 | |
| Download: ML19260A668 (5) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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Report No. 50-327/79-49 Licensee: Tennessee Valley Authority 500A Chestnut Sreet Chattanooga, Tennessee 37401 Docket No. 50-327 Facility Name: Sequoyah Unit 1 License No. CPPR-72 Inspection at Sequoyah site near Daisy, Tennessee Inspector: M#
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/c-//-7f T. J. Donat U Date Signed Approved by: //'
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/#-r&M P. T. 'Burnett',"A'ct'ing Section Chief, RONS Branch Date Signed SUMMARY Areas Inspected This routine, unannounced inspection involved 44 inspector-hours onsite in the areas of startup procedure review, closeout of previous inspector identified item, and review of coamleted preoperational test packages.
Results Of the areas inspected, no items of noncompliance. or deviations were identified.
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DETAILS 1.
Pers+ns Contacted Licensee Employees
- J. M. Ballentine, Plant Superintendent
- W. E. Andrews, Site Quality Assurance Supervisor
- S. Wilburn, Preoperational Test Section Assist Supervisor
- W. Kinsey, Jr., Results Supervisor N. B. Le, Preoperational Test Engineer D. Crisp, Assist site Health Physicist D. Kitt, Site HeaJth Physicist C. Cantrell, Assistant Plant Superintendent NRC Resident Inspector
- W. T. Cottle
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 21, 1979 with those persons indicated in Paragraph I above.
The inspector summarized the areas of his inspection and that his findings were clear in all areas.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of Startup Procedures The inspector reviewed the following unit I startup procedures for con-formance to Regulatory Guide 1.68, FSAR sections 10.3, 10.4, 12.3, 14.1, 15.1, and FSAR table 14.2.
SU-1.1, Loss of Offsite Power, Rev 2, Draft SU-1.2A, Shutdown from Outside the Control Room, Rev 1 SU-1.2B, Cooldown from Outside the Control Room, Rev 1 SU-7.1, NSSS Startup Sequence, Rev 1 SU-8.4, Incore-Excore Detector Calibration, Rev 2 SU-8.5.2, Precritical Temperature Instrumentation Offset and Linearity Check, Rev 1 SU-9.1, 10% Load Swing, Rev 1, Draft SU-9.3, Large Load Reduction Test, Rev 2, Draft 1464 430
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SU-9.4A, Plant Trip From 100% Power, Rev 3, Draft SU-9.4B, 100% Net Load Trip, Rev 3, Draft SU-9.5, Rod Group Drop and Plant Trip, Rev 2 SU-10.1, NSSS Acceptance Test, Rev 1 SU-10.2, Steam Generator Moisture Carryoner Test, Rev 2, Draft The inspector identified minor corrections to the various procedures to the licensee who had them changed.
6.
Followup of Previous Inspect. ion Findings a.
Closed Open Item 77-33-02 concerning the receipt and placement of energizing cabinet equipment throughout the plant.
The inspector examined the emergency equipment cabinets in the main control room, communications room, HP laboratory, gate house and meteorological building, and verified that correct material was located in each cabinet. This item is closed.
b.
Closed Open Item 77-33-03 concerning placement of self contained breathing apparatus (SCBA) in the emergency cabinets, completion of air testing the compressor and verification of respirator training for site personnel. The inspector reviewed the respirator training records in the site health physics office for a sample of site personnel and, verified the presence of SCBA's in each site emergency cabinet and the performance of the compressor air test. This item is closed.
c.
Closed Open Item 77-33-04 concerning the need for a seismic monitoring preoperational test, TVA-52. ine inspector reviewed preoperational test procedure TVA-52, " Seismic Instrumentation", as well as change notice #1 and #2. The test utilizes site Surveillance Instruction-125 to perform the actual calibration of the seismic monitors. The inspec-tor reviewed SI-125 and had no comments. The inspector identified numerous discrepancies in monitor designations between the preopera-tional test end the test record drawing. Thesefthe licensee corrected with change notice #2.
Based on the above this item is closed.
d.
Closed Open Item 77-33 concerning the need for a decontamination facility including an area for medical emergency treatment. The inspector toured the decontamination facility including medical treatment area, decontamination shower stall, decontamination supply cabinet and medical supply cabinets.
Based on this the item is closed.
e.
Closed Open Item 79-33-06 concerning verification of installation of fire detectors and satisfactory completion of preoperational test TVA-25A. The inspector reviewed the test package for TVA-25A, and noted that test was not complete but all items within were being properly resolved. Based on the action to date this item is closed.
f.
Closed Open Item 77-33-07 concerning the staging of a radiological emergency kit in the site ambulance, staging of the ambulance inside 1464 331
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the secured area and revising exhibit 14 to the TVA-MAP portion of the site R.E.P. The inspector verified that the site ambulance is staged in the service building passegeway and that the radiological emergency kit is now stored insided it.
Also exhibit 14 to the TVA-MAP has been changed to delete the n::d to have a second emergency kit staged at the guardhouse.
Therefore this item is closed.
g.
Clos 7d Open Item 79-33-13 concerning the installation of the environ-mental monitoring station and completion of preoperational test TVA-33.
The inspector reviewed the completed preoperational test data package for TVA-33, " Environ Radiation Monitoring System," and noted that the test had been properly completed and no outstanding deficiencies existed. This item is closed.
h.
Closed Open Item 79-33-14 concerning the placement of copies of the site Radiological Emergency Plan (R.E.P.) in all of the site's emer-gency cabinets. The inspector examined all of the sites's emergency cabinets as discussed in paragraph 6.a and copies of the site's R. E.P. were found in each. This item is closed.
i.
Closed Open Item 79-33-15 concerning providing security and health physics training for local police and fire department personnel. The inspector reviewed records for training provided on 3/2-5/77, 5/11/77, 6/30/78/ 11/9/78 and 8/15/79 to various local agencies including the Soddy-Daisy Fire and Police Department, the Hamilton County Police Department, the Chattanooga Fire Department and the Tennessee Highway Patrol. Also physical security instruction Phy SCI-13 in section 3.5 defines a yearly plan to train local police and fire personnel. This item is closed.
j.
Closed Open Item 77-33-16 concerning the performance of a radiation emergency drill. The inspector reviewed the documentation from the drill performed on June 12, 1979, including I&E inspection report 50-327/79 -33 This item is closed.
k.
Closed Open Item 76-04-01 concerning the adequacy of preoperational test TVA-52, " Seismic Instrumentation System".
Based on the review presented in paragraph 6.c.
this item is also closed.
1.
Closed Open Item 78-43-02 concerning identification of bypass-leakage paths for dual containment facilities as discussed in the Kniel letter of August 8, 1975. The bypass-leakage paths used by the licensee in the integrated leakage rate test (ILRT) report is consistent with the leakage paths specified in the 3/1/79 and 9/1/79 " proof and review" copies of the unit I technical specifications. Therefore this item is closed.
m.
Open Item 79-25-01 concerned the differences between technical specifi-cation 3.2.2, FSAR section 5.3, and preoperational test W-1.8 in addressing minimum acceptable loop flow. The inspector reviewed a copy of Westinghouse letter TVA-7536 dated July 18, 1979 in which the i464 332
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best-estimate loop flow and thermal-design flow were revised to 97000 gpm and 91400 gpm respectively. The licensee has indicated that an FSAR amendment to incorporate these new numbers will be submitted.
The inspector discussed how these numbers would be utilized in the preoperational test, W-1.8, and the surveillance test, SI-155.
In both cases the acceptance criteria must be that the calculated loop flow rate after accounting for measurement inaccuracies must be greater than the thermal design flow rate. The licensee acknowledge this comment.
The inspector will review these documents at a later date, when they have been revised to take into account the measurement inaccuracies and the new thermal design flow rate.
7.
Movement of New Fuel On September 13, 1979 the inspector watched the merement of new fuel assemblies from the new fuel storage vault to the spent fuel pit storage racks. This movement was in preparation for subsequent loading of fuel into the unit I reactor vessel and receipt onsite in mid-October of new fuel for unit 2.
The inspector verified that an approved copy of the fuel handling procedure, FH-1, and the fuel transfer checklist were in use.
The inspector monitored the transfer of the first two fuel assemblies, and had no comments on the operations.
8.
Plant Tour The inspector toured the unit I reactor containment, the auxiliary building and the turbine building.
General cleanliness and housekeeping were observed and no item of noncompliance or deficiencies were observed.
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