ML20211H159
| ML20211H159 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/17/1987 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8702260094 | |
| Download: ML20211H159 (3) | |
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol SN 157B Lookout Place FEB 171987 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention:
Dr. J. Nelson Grace In the Natter of
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Docket Nos. 50-327 Tennessee Valley' Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - NRC-0IE REGION II INSPECTION REPORT NOS. 50-327/86-60 AND 50-328/86-60 Enclosed is our response to Gary G. Zech's January 16, 1987 letter to S. A. White which transmitted NRC Inspection Reports 50-327/86-60 and 50-328/86-60. This response is provided to address the results of our corrective action review for the cited example of Violation 50-327, -328/86-19-06.
Our response is provided in the enclosure.
If you have any questions, please call G. B. Kirk at 615/870-6549.
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To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours.
TENNESSEE VALLEY AUTHORITY
)J.A.Domer,AssistantDirector
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Nuclear Safety and Licensing Enclosure cc:
See page 2 8702260094 870217 DR ADOCK 05 g7 f
I l An Equal Opportunity Employer
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- U.S. Nuclear Regulatory Commission fh f f hf cc (Enclosure):
Mr. J. J. IIolonich Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. James Taylor, Director office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. B. J. Youngblood U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. G. G. Zech, Director TVA Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy Tennessee 37319
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ENCLOSURE 5
RESPONSE - NRC-0IE INSPECTION REPORT i
NOS. 50-327/86-60 AND 50-328/86-60 CARY G. ZECH'S LETTER TO S. A. WHITE DATED JANUARY 16, 1987' l
As requested in the subject inspection report, we have reviewed our corrective actions for Violation 50-327, -328/86-19-06 to ensure that these actions also 4
address the concerns identified in the cited second example of Violation 86-19-06.
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As identified in our response to Violatior. 86-19-06, the root cause for the violations has been identified as personnel error, in that in each case, personnel failed to follow procedures which were established to accomplish activities affecting quality. The example of Violation 86-19-06 cited in
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Inspection Report 86-60 resulted from personnel not adequately following Engineering Procedure ENDES-F? 3.10, which resulted in the inadequate review i
of drawing 47W610-68-7, Revision 5.
This in turn led to the lack of adequate Postaccident Monitoring (PAM) instrumentation in the control room.
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j The problem was initially corrected by Temporary Alteration Change Form (TACF) l 1-84-83-68.
This rescaled PI-68-66 to 0-3000 psig. The permanent fix'was.
I accomplished by Field Change Request (FCR) 2634 under the original Engineering
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Change Notice (ECN). This returned PI-68-66 to a range of 0-600 psig and l
placed a second indicator in the PT-68-66 loop for PAM indication with a range of 0-3000 psig.
l In the response to Violation 86-19-06 TVA committed to identify modification criteria for all modifications after January 15, 1986, to establish a design l
basis for each plant modification.
TVA implemented Nuclear Engineering
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Procedures (NEPs) 5.1, 5.2, and 6.1 on July 1, 1986, which are the upper-tier documents governing specific SQN Engineering Procedures (SQEPs). These l
upper-tier procedures establish methods of preparing and reviewing design output and a method of controlling changes. Specifically, SQEP-13, 1
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" Transitional Design Control Process," has been issued.
Under this process, i
the modification is issued as a supplement to a design basis drawing. The change package includes all applicable design criteria and modification criteria. Also,;the Unreviewed Safety Question Determination (USQD) is written at the end of the design process just before the package is issued to
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the constructor. This will allow a final global review of the modification to ensure all criteria and commitments are satisfied.
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