ML19308D700
| ML19308D700 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point, Crystal River  |
| Issue date: | 12/10/1971 |
| From: | Jennifer Davis US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| 15259, NUDOCS 8003120839 | |
| Download: ML19308D700 (3) | |
Text
1 s*Nf*t UNITED STATES
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ATOMIC ENERGY COMMISSION j. " T 'b '. j DIVISION OF COMPLIANCE REGiCNti - Su e T E 816
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230 P E ACHT R E E ST R EET, NCRT HWEST T
uou He403 g 46 AT L A NT A, GEOHCI A 30303 In Reply Refer to:
December 10, 1971 C0:II:50-302 Florida Power Corporation Attn: Mr. J. T. Rodgers Nuclear Project Manager 101 P_ith Street South P.O. Box 14042 St. Petersburg, Florida 33733 Gentlemen:
We recently received information from the Florida Power and Light Company concerning an occurrence during preoperational testing of the Turkey Point 3 pressurized water reactor which may relate to the performance of steam line pressure relief valve headers in your facility.
V This letter provides you with a copy of the body of a telegram sent to all operating reactors by cognizant Regional offices of the Division of.Conpliance.
For your reactors which are not yet licensed to operate, no response to this letter is required of you. We will review this matter during our continuing inspection program.
- Should you have any questions concerning this matter, we will be pleased to discuss them with you.
Very truly yours,
)
John G. Davis k Director
Attachment:
Body of Telegram t)b' pl-p u we '
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BODY OF TELEGRAM TO LICENSEES OF OPERATING POWER REACTORS We recently received information from the Florida Power and Light l
Company of an occurrence during preoperational testing of the Turkey Point 3 Westinghouse pressurized water reactor that may relate to performance of the steam supply system at your facility.
- Thit informatica is as follows:
1 During hot functional. testing cf the unfueled reactor, three i
of four relief valves were catastrophically ejected from two i
main steam line heeders, to which they were mounted. The failed headers were 12-inch. diameter, spool pieces fabricated by the Dravo Corporation, Marietta, Ohio, from Schedule 60 j
(.562-inch wall thickness) A106, Grade B carbon steel pipe j
manuf actured by U. S. Steel, Lorain Works,. Lorain, Ohio, mounted l
horizontally,180* from each other, on the two sides of the l-main steam line.
The headers were hyarostatically tested at 1356;psig under cold conditions prior to hot functional j
tes ting. On one side of the main steam line, the failure occurred in the vicinity of the heat affected zone of the l
weld which joins the riser to the header and appears to be largely confined'to the 12-inch header. On the other side of the main steam line, the failur apparently originated in a similar manner and propagated through the pipe header
+
causing catastrophic damage to the header assembly. The secondary system was at 990 psig and 545*F and the primary system at 2232 psig and 546.6*F at the time of the header failure. These systems had been at their respective pressures and temperatures for nise days. No transient conditions were reported to have existed in these systems at the time of failure.
The. failed header assemblies each consist of two valves mounted 1-vertically in a dead-end,12-inch diameter pipe projecting at a i
90* horizontal angle from the main steam line. The two headers are 4
- mounted at 180* to 'each other on the opposite sides of the main steam line. The headers were designed to meet Section I of the ASME Code i
by the Bechtel Corporation, For your reactors which are licensed to operate, it is requested that you provide this office within ten days, in writing, as to whether headers as described above are installed in the steam lines of your i
facility.
l Should you have any questions concerning this matter, we will discuss 1'
-them with you.
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5 Letter to Florida Power Corporation dated December 10, 1971 DISTRIBUTION:
J. B. Henderson, CO (6) C q
A. Giambusso, CO L. Kornblith, Jr., C0 R. H. Engelken, C0 DR Central Files P. A. terris, DRL D. J. Skovholt, DRL R. C. DeYoung, DRL R. S. Boyd, DRL H. R. Denton, DRL 4
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