ML20078P851
| ML20078P851 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 11/02/1983 |
| 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, NCR-8311, NUDOCS 8311090189 | |
| Download: ML20078P851 (2) | |
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Y TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374ol 400 Chestnut Street Tower II 8f 4 $,.
November BLRD-50-438/83-53 BLRD-50-439/83-46 U.S. Nuclear Regulatory Commission 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 - SIZE OF LINES OF FLOW RESTRICTORS IS ABOVE THAT WHICH ENSURES A CONTROLLABLE COOLDOWN PER FSAR -
- BLRD-50-438/83-53, BLRD-50-439/83 FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Linda Watson on October 6, 1983 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8311. Enclosed is our first interim report. We expect to submit our next report by May 16, 1984.
If you have any questions, 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 cc: Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nucicar Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8311090199 831102
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{DRADDCK 0500043s PDR OFFM A 1983-TVA SOTH ANNIVERSARY
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An Equal Opportunity Employer
,v ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 SIZE OF LINES OF FLOW RESTRICTORS IS ABOVE THAT WHICH ENSURES A CONTROLLABLE C00LDOWN PER FSAR BLRD-50-438/83-53, BLRD-50-439/83-46 NCR 8311 10 CFR 50.55(e)
FIRST INTERIM REPORT Description of Deficiency There is a discrepancy between the FSAR stated break size that will ensure a controllable cooldown and that specified by the design criteria and the design drawings. FSAR sections 9.3.6.1 (page 9 3-41), 9 3.6.3 (1) (page 9.3-58) and 9'.3.6.3 (2g) (page 9 3-60) specify an opening equivalent to a 3/4-inch schedule 160 pipe (0.614-inch inner diameter (ID)) as the break size which will ensure a controllable cooldown. However, Design Criteria for the Classification of Piping, Pumps, Valves, and Vessels, N4-50-D754 R0, specifies a 3/4-inch ID (section 3.7, oage 8) for sensing, sampling, and radiation monitoring lines. This is based on the normal makeup capacity of the makeup and purification system and is intended to meet 10 CFR 50 Appendix A, General Design Criterion 33 It is also the basis for the flow restrictor that permits the classification change from ASME Section III class 1 to ASME Section III class 2 per 10 CFR 50.55 a(d),
footnote 2.
This also agrees with Babcock and Wilcox (B&W) letter D-2424 dated March 10, 1977, in which B&W stated that a break larger than 3/4-inch must be ~ considered as a LOCA sized break. Likewise, the 3BWO422-NK series drawings for the reactor coolant drain and vent system have a number of flow restrictors larger than 0.614-inch ID, and drawings 3BWO422-NK-05 R9 (section B-B, detail A) and 3BWO422-NK-09 R8 (Section A-A) show 3/4" ID flow restrictors, all of which are in agreement with the design criteria.
It has been found that flow restrictor ASME classification specified by the design drawing does not agree with that specified by the design criteria diag ram. Drawings 3BWO422-NK-07 PB (Section E7-E7) and 3BWO422-NK-08 R10 (section F-F) show 1-inch x 3/4 inch schedule 80 reducers (0.742-inch ID) welded at the small diameter. The reducers are te ASME Section III class 2.
However, the upstream reducer should be to ASME Section III class 1 per Design Criteria Drawing (DCD) 3BWO622-NK-01 R8. The deficiency of the ASME classification difference between reducers can be attributed to an error in the detailed piping design whereby the wrong mark numbers were assigned to the reducers.
Interim Proeress TVA is evaluating and investigating the break size discrepancy, and has requested B&W, the RCS designer, to resolve this discrecancy, I