ML20024G476
| ML20024G476 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/23/1977 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G467 | List: |
| References | |
| 50-263-77-13, NUDOCS 9102120528 | |
| Download: ML20024G476 (1) | |
See also: IR 05000263/1977013
Text
y a/
e
.
-
-
.
.
(3)
Committee review of proposed tests and experiments
are in accordance with 10 CFR 50.59.
,
(4)
Technical Specifications changes are reviewed as
J
required.
Review of the Operations Committee records indicated that
1
the licensee is not formally reviewing and documenting
Technical Specifications violations as required by Sections
VI.2.B.4.e and VI.2.B.6 of the Technical Specifications.
Specifically, noncompliance items in IE Inspection Report
Nos. 50-263/76-18, 77-01, 77-05, 77-06, 77-07 and 77-10-
apparently were not reviewed and documented by the
Operations Committee.
b.
The inspector reviewed the audit programs conducted by the
Safety Audit Committee, the corporate Quality Assurance
group, and the plant Quality Assurance group, and determined
that audits are being conducted as required by Technical
Specificatione and the licensee's administrative instructions.
Review of audits performed by the plant during the past year
identified four items requiring corrective actions which
have been accomplished or are in the process of being
accomplished.
3.
Reactor Building Crane Modifications
The licensee has completed the installation of a new trolley on
the reactor building crane. The new trolley provides redundant
hoist lifting cables. The Division of Operating Reactors approved
modifications to the reactor building crane in a letter to the
.licenset dated May 19, 1977.
The inspector reviewed the licensee's procurement specifications,
licensee audits of the crane trolley vendor, licensee audits of
the installation contractor, installation procedures, preoperational
test procedures, vendor functional test results, and the design
change package associated with the reactor building crane modifica-
,
'
tions.
Review of the preoperational testing indicated that certain
testing that the licensee intended to perform as stated in their
submittal to the NRC (NSP Licensing Report, NSC-LS&R-NOR-0151-17,
dated November 11, 1976, and submitted November 22, 1976) had not
been completed as follows:
t
a.
No Load Test
Check for proper engagement of bridge and trolley with the
i
stops at the end of the girders.
I
i
!
t
-3-
(
l
9102120528 770923
ADOCK 05000263
G