ML20079H883
| ML20079H883 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 01/13/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8401240097 | |
| Download: ML20079H883 (2) | |
Text
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s TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374of 400 Chestnut Street Tower II
^ 9 inda5y 13,1984 B4 JANlo J
BLRD-50-438/82-09 BLRD-50-439/82-09 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 l
Atlanta, Gew gia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - TEMPERATURE OF NITROGEN SUPPLY -
BLRD-50-438/82-09, BLRD-50-439/82 FIFTH INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector D. Johnson on January 14, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8201. This was followed by our interim reports dated February 17, April 27, and August 12, 1982 and March 29, 1983 Enclosed is our fifth interim report. We expect to submit our next report on T about August 29, 1986.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY
, if.h L. M. Mills, Wanager Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Babcock & Wilcox Company (Enclosure)
P.O. Box 1260 Lynchburg, Virginia 24505 Attention:
Mr. R. J. Ansell Racords Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339
, g '." M L G ' M 8401240097 840113 Jg g 7 PDR ADOCK 05000438 B
PDR I
I l 1983-TVA SOTH ANNIVERSARY An Equal Opportunity Employer
i ENCLOSURE I
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 TEMPERATURE OF NITROGEN SUPPLY NCR BLN BLP 8201 BLRD-50-438/82-09, BLRD-50-439/82-09 10 CFR 50.55(e)
FIFTH INTERIM REPORT Description of Deficiency Nitrogen is used as a cover gas for various safety-related pieces of equipment, such as the reactor coolant system, -pressurizer, steam generator, and core flood tanks. B&W document No. 67-1003781-00, " Plant Limits and Precautions," lists the minimum temperature reqairement of nitrogen to be supplied to these pieces of equipment. Contrary to the above requirements, the present nitrogen system design supplies nitrogen below the required temperature.
B&W document No. 67-01003781-00 was issued in 1978, well after development of the design of the nitrogen system. Since the document did not directly relate to the nitrogen system design, it was not routed to the nitrogen system designers for their review. This condition went unnoticed until a design review of one of the systems that interfaces with the nitrogen system.
Interim Progress Procurement specifications for the nitrogen heaters and mechanical installation drawings have been issued. Heaters have been delivered to the plant site and installed. Electrical drawings have been issued, but wiring to the heaters remains to be completed. After completion of analysis of the nitrogen supply system piping by TVA's Civil Engineering Branch to the new higher temperatures, supports on the piping will be redesigned for units 1 and 2.
All interfacing systems must be reanalyzed using both rigorous and alternate analysis. Also, new load tables must be established.
Reanalysis and pipe support design involves problems NV-F, SV-R, an SV-T for both units 1 and 2.
This work is proceeding under engineering change notice 1390.
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