ML17261A571
| ML17261A571 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/30/1987 |
| From: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17261A572 | List: |
| References | |
| IEB-79-02, IEB-79-2, NUDOCS 8708060244 | |
| Download: ML17261A571 (8) | |
See also: IR 05000244/1987011
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCE/SION NBR: 8708060244
DOC. DATE: 87/07/30
NOTARIZED:
NO
DOCKET
=ACIL: 50-244 Robert
Emmet Ginna Nuclear Planti
Unit ii Rochester
G
05000244
AUTH. NAME
AUTHOR AFFILIATION
JOHNSTON'. V.
Region ii Office of Director
RECIP. NAME
RECIPIENT AFFILIATION
KOBERi R. W.
Rochester
Gas
5 Electric Corp.
SUB JECT:
Forwards
Sa fet'nsp
Rept 50-244/87-11
on 870505-08
5 notice
of violation. Response
documenting
scope
5 results
of static
,'quivalent
analyses> anchor bolt replacements
4 schedule for
.completion
of long-term seismic
upgrade
program requested.
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED: LTR
ENCL
SIZE:
TITLE: General
(50 Dkt)-lnsp Rept/Notice of Violation Response
NOTES: License
Exp date
in accordance
eith
10CFR2i 2. 109(9/19/72).
05000244
RECIPIENT
ID CODE/NAME
PDi-3
INTERNAL: AEOD
MQR ISSEAUi D
NRR/DREP/EPB
NRR/DRIS DIR
0
MANiJ
REG
F ILE
1
FILE
01
COPIES
LTTR ENCL
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
RECIPIENT
ID CODE/NAME
STAHLEi C
DEDRO
NRR/DOEA DIR
NRR/DREP/RPB
NRR/PMAS/ILRB
OGC/HDS2
DEPY GI
COPIES
LTTR ENCL
2
2
1
1
1
1
2
2
1
1
1
1
1
EXTERNAL:
LPDR
NSI C
NRC
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
20
ENCL
20
Docket No. 50-244
Rochester
Gas
and Electric Corporation
ATTN:
Mr. Roger
W. Kober
Vice President
Electric and
Steam Production
49 East
Avenue
Rochester,
14649
Gentlemen:
Subject:
Inspection
No. 50-244/87-11
This letter refers to the safety inspection
conducted
by Mr. A. A. Varela of
this office on
May 5-8,
1987 at the Rochester
Gas
and Electric Engineering
office and the
R.
ED Ginna plant site.
Mr. Varela discussed
the findings of
the inspection with Mr. B. A.
Snow at the conclusion of the inspection
and with
Messrs.
G. Wrobel
and
M. Lilley in a subsequent
telephone call
on
May 22,
1987.
Areas
examined during this inspection
are described
in .the
NRC Region I
Inspection
Report enclosed with this letter.
Within these
areas,
the inspec-
tion consisted of selective
examinations of procedures
and representative
records,
interviews with personnel,
and observations
by the inspector.
Based
on the results of this inspection, it appears
that
some of your
activities were not conducted
in full compliance with commitments
made
by
Rochester
Gas
and Electric Company in response
to
(See
Notices of Deviation enclosed
herewith
as Appendix A.)
Specifically, our
inspection
determined that ( 1) the factors of safety for pipe support
base
plate anchor bolts in certain portions of the Standby Auxiliary Feedwater
and
the
Emergency Service Water systems
had not been evaluated
and (2) anchor
bolts in five pipe support
base plates
in portions of those
same
systems
had
not been reinspected
subsequent
to system
modifications'n
June
15,
1987, Messrs.
C. J. Cowgill and J.
R. Strosnider of this office
discussed
the above findings with Mr. P.
C.
Wi lkens
and other members of your
staff.
Based
on that telephone
conversation, it was our understanding
that
you would take the following actions to'fulfill the commitments
made in
response
1.
Static equivalent, analyses willbe performed
by July 6,
1987 to
demonstrate
that the subject
unanalyzed
base plate anchor bolts meet the
established
minimum factor of. safety of 2.0.
8708060244
870730
ADOCK 05000244
G
'OFFICIAL RECORD
COPY
IR GINNA 87-11
0001.0.0
I
~
05/26/87
2 V'
Rochester
Gas
and Electric Company
2.
Anchor bolts in the five piping support
base plates for which loads
have
changed
from compression
to tension
as
a result of the seimic upgrade
program will be replaced within 60 days
from June
15,
1987.
Subsequently,
Mr. P. Wilken and other members of your staff informed
Messrs
C. Cowgill and J. Strosnider of this office that the static equivalent
analyses
described
in
1 above
had been
completed
and that the factors of
safety for the subject anchor bolts all satisfied the established
acceptance
criteria.
You are required to respond to this letter.
In preparing your response,
you
should follow the instructions in Appendix A.
In addition, your response
should document
the
scope
and results of the analyses
described
in 1, above;
provide the status of the anchor bolt replacements
described
in 2, above;
and
provide your schedule for completion of the Ginna long term seismic
upgrade
program.
The responses
directed
by this letter and the accompanying
Notice are not
subject to the clearance
procedures
of the Office of Management
and Budget
as required
by the Paperwork Reduction Act of 1980,
PL 96-511.
Your cooperation with us in this matter is appreciated.
Sincerely,
William V. Johnston,
Acting Director
Division of Reactor Safety
Enclosures:
l.
Appendix A, Notice of Deviation
2.
NRC Region I Inspection
Report
No. 50-244/87-11
cc w/encl:
Harry H. Voigt, Esquire
Central
Records
(4 copies)
Director,
Power Division
Public Document
Room (PDR)
Local Public Document
Room (LPDR)
Nuclear Safety Information Center
(NSIC)
NRC Resident
Inspector
State of New York
OFFICIAL RECORD
COPY
IR
GINNA 87-11
0001.0. 1
05/26/87
'
Rochester
Gas
and Electric Company
bcc w/encl:
Region I Docket
Room (with concurrences)
Management Assistant,
DRMA (w/o encl)
DRP Section Chief
Robert J.
DRSS
Varela/bc/rw
07/5%87
I:
RS
Gregg
07/g+87
~W/Zp
RI: DRS
RI: DRP-
Strosnider
owgill
07/g~/87
07/4<87
OFFICIAL RECORD
COPY
IR GINNA 87-11
0001.1.0
05/26/87