ML20055B772

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Second Interim Deficiency Rept Re Incorrect Installation of Pressure Relief & Safety Valves,Initially Reported on 820305.Design Criteria & Physical Drawings Will Be Issued by 821004.Next Rept Expected by 830110
ML20055B772
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 07/13/1982
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 8207230286
Download: ML20055B772 (2)


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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II July 13, 1982 BLRD-50-438/82-25 BLRD-50-439/82-22

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U.S. Nuclear Regulatory Commission Attn:

Mr. James P. O'Reilly, Regional Administrator 45 Region II

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g 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

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Dear Mr. O'Reilly:

cs BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - INCORRECT INSTALLATION OF PRESSURE RELIEF AND SAFETY VALVES - BLRD-50-438/82-25, BLRD-50-439/82

  • SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Don Quick on March 5, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8210. This was folllowed by our first interim report dated April 2, 1982. Enclosed is our second interim report. We expect to submit our next report by January 10, 1983.

If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.

Very truly yours, TENNESSEE VALL AUTHORITY l

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. M. Mills, Manager Nuclear Licensing Enclosure cc:

Mr. Richard C. DeYoung, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission i

l Washington, DC 20555

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PDR ADOCK 05000438 S

PDR An Equal Opportunity Employer g

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8 ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 a-INCORRECT INSTALLATION OF PRESSURE RELIEF AND SAFETY VALVES 10 CFR 50.55(e)

BLRD-50-438/82-25, BLRD-50-439/82-22 NCR BLN BLP 8210 SECOND INTERIM REPORT Description of Deficiency Condition I - The two relief valves on the component cooling water supply lines to the shell side of the letdown coolers discharge into a common waste disposal drain header. The waste disposal header is not sized to accommodate both relief valves. Also, there are several other smaller l

relief valves discharging into this same waste disposal header. This condition applies to units 1 and 2.

Condition II - Two relief valves on the component cooling water piping for the coolers to reactor coolant pump P1A1 discharge into a common line which is sized too small to acconnodate both relief valves. This condition applies to unit 1 only.

These conditions violate ASME Code Section III, Division I, ND-3677.3d(2).

Interim Progress Condition I - TVA has determined that the proposal to route the letdown cooler relief valve drains to the reactor coolant drain tank instead of the reactor building normal sump as orginally designed is not a viable solution. An alternate solution has been proposed and approved by TVA.

This solution replaces one of the 6-inch relief valves with a smaller valve set at a lower set pressure and drains it to the waste disposal headers as originally designed. This valve would be sized so as not to violate the ASME Code. The other 6-inch relief valve would relieve to containment and would be set at a higher set pressure than the smaller valve. With this valving arrangement, the radioactive fluid from a small tube rupture would be completely contained. The radioactive fluid from a large tube rupture of the letdown cooler would be released inside containment and processed through the containment sump /radwaste systems.

TVA is proceeding with the alternate solution. Revision of the design criteria and physical drawings are scheduled to be issued by October 4, 1982. TVA is writing the specification for the smaller relief valve to send to procurement.

Condition II - The size of the common drain line from the two relief valves will be increased to accommodate flow from both relief valves.

The design criteria and physical drawings are scheduled to be issued by October 4, 1982.

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