PNO-II-87-019A, on 870322,NRC Informed That Insp & NDT of Reactor Head Closure Studs Indicated Exterior Corrosion & Evidence of Internal Thread Wasting.Reactor Head Will Be Removed for Insp
| ML20205G167 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/23/1987 |
| From: | Brewer R, Christensen H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-II-87-019A, PNO-II-87-19A, NUDOCS 8703310387 | |
| Download: ML20205G167 (1) | |
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1 March 23, 1987 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-87-19A i
FACILITY:
Florida Power & Light Company Licensee Emergency Classification i
Turkey Point Unit 4 Notification of Unusual Event 1
Docket No.: 50-251 Alert Homestead, Florida Site Area Emergency General Emergency X Not Applicable i
SUBJECT:
AIT DISPATCHED TO TURKEY POINT (UPDATE) l This PN updates PNO-II-87-19, issued Wednesc'ay, March 18, 1987.
The licensee informed the NRC's Augmented Inspection Team (AIT) on Sunday,
~
March 22, 1987, that inspections and nondestructive testing of reactor head closure studs, affected by a small reactor coolant system leak on the flange connection of an instrument penetration to the reactor vessel head, show exterior corrosion and evidence of internal thread wasting. The licensee has commenced work to remove the reactor head in order to perform a complete inspection. The licensee will replace affected closure studs, locking nuts and washers, along with the entire reactor head CRDM shroud (which was damaged by the boric acid). It will also inspect internal threads in the stud receptacles on the reactor flange for evidence of thread wastage.
NRC inspectors have been inside containment to evaluate the adequacy of tests i
as they have been conducted.
The NRC has asked the licensee for further i
chemical analyses of the crystalline material deposited by the leak for evidence of chlorides or other corrosive elements and has the licensee's commitment to thoroughly examine other instrumentation and equipment for signs i
of exposure.
The licensee has confirmed deposits in the ductwork of the control rod drive mechanism cooling fans.
The licensee estimates removal of the reactor head, inspection of affected instruments and equipment, and replacement of the shroud and corroded studs and nuts will take approximately 27 days. Replacement studs from adjacent Unit 3, which is down for refueling and maintenance, will be used. New replacements j
have been ordered from Westinghouse.
The NRC team leader has requested that the licensee make available to the NRC i
one of the affected studs af ter its removal for use in the evaluation related to possible generic implications.
Area media interest continues.
The licensee and the NRC have responded to
'j numerous media inquiries. The licensee issued a press release and Region II dispatched a Public Affairs Officer to the site to assist with media relations.
The licensee and the NRC have tentatively scheduled a joint news conference at 11:00 a.m.
(EST) today.
Media representatives will be shown models and actual examples of affected components.
The licensee plans to provide video tapes of the affected area if available.
The State of Florida is being kept informed.
l This PN is being issued for information purposes only. The information is current as of 8:00 a.m. (EST) on March 23.
23 ma 8; jpjQNTACT:
H. Christensen, RII 242-4497 R. Brewer, 305-245-7670
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0703310307 870323 r
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{' l Ph0-II-87-019A PDR