ML17263A215
| ML17263A215 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1993 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17263A216 | List: |
| References | |
| NUDOCS 9304140017 | |
| Download: ML17263A215 (3) | |
See also: IR 05000244/1993005
Text
FIATS 3 0 i993
e
Docket No. 50-244
Dr. Robert C. Mecredy
Vice President,
Ginna Nuclear Production
Rochester
Gas and Electric Corporation
89 East Avenue
Rochester,
New York 14649
Dear Dr, Mecredy:
'UBJECT'NSPECTION REPORT NO. 50-244/93-05
This letter refers to the inspection conducted by Mr. J. Carrasco of this office on
February 16-19, 1993, at your offices in Rochester,
New York. The inspector discussed
the
results of the inspection with Mr. G. Wrobel and other members of your staff at the
conclusion of the inspection.
This inspection focused on activities important to the public health and safety and was
directed towards engineering and operation activities with emphasis
on the adequacy of
modification EWR 5275, "Replacement of Containment Recirculating Fan Coolers," and
modification EWR 5411, "Service Water Temporary Cooling."
Details on the areas examined during the inspection are described in the NRC Region I
inspection report, which is enclosed with this letter.
Within these areas,
the inspection
consisted of selected examinations of procedures
and representative
records, interviews with
personnel,
and observation by the inspector.
Within the scope of this inspection, no violations were observed.
Your staff performed the
pertinent analysis to demonstrate
that the replacement of containment recirculation fan
coolers meets the General Design Criterion 38.
Based on the preliminary assessment
regarding the loads on the diesel generator (D/G) resulting from the new CRFC, it appears
that these loads would not adversely affect the D/G.
Commitments made by your staff {RG&ENos. RO1968 and RO1969) to resolve weaknesses
identified in NRC Inspection No.91-201 Service Water System inspection were not properly
followed up.
This is unresolved pending NRC verification of a letter describing the deferral
of these two commitments to the 1994 outage.
OFFICIALRECORD COPY A:GINNA.JC
9304140027
930330
ADOCK 05000244
6
2
No reply to this letter is required.
Your cooperation in this matter is appreciated.
Sincerely,
Jacque P. Durr, Chief
Engineering Branch
Division of Reactor Safety
Enclosure:
- NRC Regioh I Inspection Report No. 50-244/93-05
cc w/encl:
R. Smith, Senior Vice President,
Production and Engineering
Central Records (4 copies)
Director, Energy and Water Division
State of New YorkDepartment of Law
N. Reynolds, Esquire
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
K. Abraham, PAO (2) All Inspection Reports
NRC Resident Inspector
State of New York, SLO Designee
OFFICIALRECORD COPY A:GINNA.JC
Dr. Robert C. Mecredy
~
~
bcc w/encl;
Region I Docket Room (with concurrences)
(w/cy of IFS Forms)
DRS/EB SALP Coordinato.
J. Linville, DRP
W. Lmrus, DRP
T. Moslak, SRI - Ginna (w/cy of IFS Forms)
V. McCree, OEDO
RI:DRS
'
a
o
3/u/93
RI:DRS
Gray
03/ll/93
RI:DRS
Durr
03/$ 93
OFFICIALRECORD COPY
A'GINNA.JC