ML20054C517

Forwards Compliance Rept 50-047/68-03 on 681028 & 29

ML20054C517
Person / Time
Site:	05000047
Issue date:	12/31/1968
From:	Moseley N US ATOMIC ENERGY COMMISSION (AEC)
To:	James O'Reilly US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML17298A033	List: IR 05000047/1971001 IR 05000047/1972001 IR 05000047/1974001 IR 05000047/1975001 IR 05000047/1976001 IR 05000047/1976002 IR 05000047/1977001 ML17298A032 ML20054C422 ML20054C424 ML20054C425 ML20054C427 ML20054C432 ML20054C440 ML20054C441 ML20054C442 ML20054C444 ML20054C447 ML20054C450 ML20054C505 ML20054C507 ML20054C511 ML20054C517 ML20054C534 ML20054C548 ML20054C554 ML20054C562 ML20054C565 ML20054C570 ML20054C571 ML20054C573 ML20054C574 ML20054C578 ML20054C580 ML20054C582 ML20054C587 ML20054C590 ML20054C591 ML20054C595 ML20054C599 ML20054C668 ML20054C672 ML20054C681 ML20054C685 ML20054C691 ML20054C696 ML20054C702 ML20054C704 ML20054C707 ML20054C709 ... further results
References
FOIA-81-311, FOIA-Z81-311 NUDOCS 8204210232
Download: ML20054C517 (1)

Text

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UNITED STATES gi o,.,,**,

ATOMIC ENERGY COMMISSION g

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olvisiON CF COMPWANCE 201 645 l

• I REGIONI 970 BROAD STMEET NEWARK. NEW srRSEY 07102 fr, p

DEC M

J.

P. O'Reilly, Chief, Reactor Inspection & Enforcement Br.,

Division of Compliance, Headquarters U. S. ARM'I MATERIALS AND MECHANICS RESEARCH CENTER DOCKET No. 50-47 The attached report of a visit on October 28'and 29, 1968, by the assigned inspector to the subject facility is forwarded for informa-tion.

No items of noncompliance or unresolved safety items were noted.

We had some reservations concerning the accuracy of the determinations of control rod worths.

We have been assured, however, that rod worth measurements will be made during the new core loading scheduled for mid-November 1968.

We intend to follow this matter closely to assure that meaningful rod worth information is available at all times in the future.

The fact that only one isolation valve is installed in both the inlet and outlet containment ventilation lines, has been discussed by the inspector with Mr. Shapaker of DRL.

We were informed that DRL would evaluate this condition in considering the licensee 's request for an authorization to increase power.

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N. C. Moseley, Senior Reactor Inspector 1

Enclosure:

CO Report No. 47/68-3 by G. L. Madsen, dtd 11/25/68 cc:

E. G. Case, DRS R.

S.

Boyd, DRL (2)

S. Levine, DRL (6)

D. J. Skovholt, DRL (3) l L. Kornblith, Jr., CO Regional Directors, CO REG files fh 4 g 32 811G05

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