ML20087A955
| ML20087A955 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/29/1969 |
| From: | Robert Carlson US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 NUDOCS 9508070238 | |
| Download: ML20087A955 (2) | |
Text
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.sw44 Cctober 29, 1969 tt l
J.
D. O'Reilly, Chiof, Reactor Inspcction & Enforcement Br.,
Division of Couplinuco, Headquarters 4
kj JnRSLY CElm M -PC'.CR & I.IGHT COMPANY DOCnD: HO.50-2L9/gy~e Ohc attached report of unannounced and announced inspection j
visit to the subject facility on September 10-12 and 29-30, 1X 9, respectivnly, is forwarded for information.
No cigaificant safety items were identified; however, one item of noncompliance was noted for which a form AEC-592 was_ issued.
T.c item of noncompliance relatos to the failuro to conduct surecillance tests in accordance with the requirements of the technical specifications.
ccc position of Maintenance supervisor (previous item of non-c :..pliance) has been ascigned to Mr. Finfrock, the outgoing
'f;;;:nical Supervisor, on an interim basis estimated to bo at
_ cast until plant turnover.
Mr. Finfrock's qualifications satisfy the requirements of the license.
Mr. Ross has now l
accu.:.cd the full dutics of Technical Supervisor.
Tao results of the powcr accension test program to the time o.: tl.c inst visit are 61= cussed in detail.
One item of' si;aificance identified wuc the failure of the reactor internals vil. ration instrumentation which has precluded obtaining hot vibration data at this facility.* JC-4E are now looking to L:me Mile Point in this regard.
The report also prescats a detailed history of all scrams enparionec5 to the timo of the last visit.. Included are four I
cerc. involving the main steam initial pressure regulator with resultant unplanned opening of turbine bypass valves.**
L o most significant of those four events, scram No. 10, saw the turbine bypass system open to its fullest capacity with a
- .aquiry Memorandum No. 219/69-D, dated october 6, 1969.
- Inquiry Mesoranda Nos. 219/69-B, dated September 15, 1969, and 219/69-C,' dated Septa W r 25, 1969.
9500070238 950227 PDR FOIA DEKOK95-36 PDR
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resultant significant reactor transient.
that they will sub: sit a written Icport on this latter occurrence.
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Two instancca of rupture of,1" relief Lincs on cleanup system, l
heat c:: changers are discussed.
The caucc, lack of proper line
.l support with resultant failure by fatigue, points up a short-coming in design by the vendor, S'.;ECO,that has possible applicability to all facilitics supplied fro:a this shop.*
7 Incoloy chips, found in the radial bearing cavity of the failed.
- D" loop rceirculation pump, have been designated as the cause l
t of the original pump failure.
Although an occasion for entry j
of the chips existed, their source remains unknown.
l l
The CC-1 generator das first paralleicd with the lino on September 23, 1969, with an electrical output of 30 Mwe.
t i
R. T. Carlson Senior Reactor Inspector i
l Attachr.cnt:
CO REPORP MO. 219/69-9 by R. T. Dodds, dated 10/24/69 t
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cc:
E. G. Case, DF.3 l
l R. S. Eoyd, DE (2) i g
S. Levino, DE (6)
D. J. Skovholt, DE (3) l 4
L. F:ornblith, Jr., CO Regional Directors, CO l
RCG Filo I
t, t
20, 1969.
- Inquiry Memorandum No. 219/69-F, dated October i
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