ML20076H634
| ML20076H634 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 08/24/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8309060091 | |
| Download: ML20076H634 (2) | |
Text
.;7 TENNESSEE VALLEY AUTHORITY CHATT ANOOGA. TENNESS 1
400 Chestnut Street Tower II
^"8P/ft}h #8h 9 : 2 7 BLRD-50-438/82-53 BLRD-50-439/82-47 U.S. Nuclear Regulatory Comission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - VALVES NOT DESIGNED TO DESIGN CRITERIA - BLRD-50-438/82-53, BLRD-50-439/82 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on August 4, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8222. This was followed by our interim reports dated August 31, 1982 and March 11, 1983 Enclosed is our final report.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Enclosure l
cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 i
e309060091 830824 PDR ADOCK 05000438 S
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1983-TVA 50TH ANNIVERSARY An Equal Opportumty Employer g[g
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 VALVES NOf DESIGNED TO DESIGN CRITERIA NCR BLN BLP 8222 BLRD-50-438/82-53, BLRD-50-439/82-47 10 CFR 50.55(e)
FINAL REPORT Description of Deficiency Containment isolation valves 1YQ-IFSV-500,1YQ-IFSV-510, 2YQ-IFSV-500, and 2YQ-IFSV-510 do not conform to the design criteria N4-NI-D740 in that they should have been classified 1E and receive trained power.
They also do not meet the " automatic or remote manual" requirement of the criteria.
The deficiency was disclosed in performing the corrective action in NCR BLNQAB8101, and the apparent cause of the deficiency was a design error.
Safety Imolications Since the isolation valves are controlled solely by the hot sample ~ ~ ' '
room operator', highly radioactive 1iquid' 'could'be dumped into the
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hotwell after a Loss of Coolant Accident (LOCA) because the operator could be sampling, totally unaware of a LOCA. This condition, if left uncorrected, would violate containment integrity during accident conditions, thus adversely affecting plant safety.
Corrective Action TVA has issued engineering change notice (ECN) 1577, to change isolation valves 1YQ-IFSV-500, 1YQ-IFSV-510, 2YQ-IFSV-500, and 2YQ-IFSV-510 from non-1E power to class 1E power, and to provide an isolation signal to automatically close the isolation valves.
Under this ECN TVA has also reviewed and corrected all affected functional control logic diagrams schematics and solid-state control system cable interconnect drawinga of the sampling and water quality systems.
This deficiency only applies to the design aspect of the valves and not to the construction implementation since the valves were never installed. The date of completion for the design change was July 26, 1983 The corrected design was issued at that time and properly reflects the design criteria.
Any action (s) required to prevent recurrence will be handled by i
nonconformance report (NCR) BLNQAB8101, which deals with generic implications of failure to implement design criteria in design drawings.
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