ML19256D039
| ML19256D039 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 01/03/1975 |
| From: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Thornburg H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19256D033 | List: |
| References | |
| NUDOCS 7910160764 | |
| Download: ML19256D039 (2) | |
See also: IR 05000289/1974035
Text
.,.
-
O
- .
,
r
UNITED STATES
h}j
g,
ATOMIC ENERGY COMMISSION
'
@
g , j p.
DIR ECTO R A TE O F R EGU LATO R Y OPE R ATIO N S
]f - ~ p , pf
REGION l
- ,. >S - r
631 P ARK AVENUE
I.,
$
KING oF PRUSSI A, PENNSYLVANI A 194L6
x
w,.
_
JAN
3 1975
H. D. Thornburg, Chief, Field Support and Enforcement Branch, RO:HQ
RO INSPECTION REPORT 50-289/74-35 (Track //F14043H0)
The subject report is forwarded for Headquarters action as follows:
1.
Revision of Technical Suecifications with respect to 100% rated cower.
As noted in report Dets
'),
there is an apparent discrepancy
between the Technical Spec ___eations and the license with regard to
the limit on reactor power.
Also the regional position on this mat-
ter, which was provided to the licensee, is stated.
Our position
was based on the following:
a.
License Condition 2.c(1) is in itself explicit, and compliance
with this limit is, in our opinion, determined by heat balance
in accordance with Technical Specifications Table 4.1-1, Item 3.
b.
The Technical Specification limit of 102% power refers, in our
opinion, to power determined by the power range channels (neutron
detectors) which provide input signals to the protection system
reactor power / imbalance trip circuit.
c.
According to Technical Specifications Table 4.1-1, Item 3, when
the core heat balance and the power range channels differ by
more than 2%, the power range amplifier for the affected chan-
nel(s) must be recalibrated.
Therefore, core power by heat
balance could be 2535 MWt (licensed power) and core power by
power range monitors could be 102%, the license and Technical
Specifications would be adhered to, and the apparent discrepancy
referred to disappears.
We believe that the proper method of clearing up this matter, is by
an appropriate change to Section 3 of the Technical Specifications,
i.e., defining a new LCO.
We would like to see a specification
which addresses core power limit, as identified in the facility
license, the method for determining core power, and the actions re-
quired when this limit is exceeded. Additionally, this recommenda-
tion should be applied generically for inclusion in Standard
Technical Specificationc currently being developed by DL and to
.
other facilities which, like Three Mile Island, are not explicit
} 44 g
} }()
in this regard.
5 0010
7910160
,.
.
I
d
-
,
.
H. D. Thornburg
-2-
.
.
2.
Revision of Technical Specifications with respect to shock supptessor
surveillance.
As noted in report Detail 2.b(8), several snubbers were found with
very little fluid in their reservoirs, and the licenaee's resolution
of this specific problem and long term corrective actions are dis-
cussed.
Other similar failutes have been reported by the licensee
(Abnormal Occurrence Reports Nos. 50-289/74-14, 74-20 and 74-23)
and additional commitments are described in these reports.
These failures were detected during surveillance inspections started
by the licensee in August 1974 as a result of suggestions made by
our inspector because Technical Specifications Table 4.1-2, Item 11
only requires inspection at refueling intervals.
Additionally,
Calvert Cliffs Technical Specifications Table 4.2-2, Item 24 also
requires inspection at refueling intervals.
We believe that refueling interval inspections are inadequate based
on Met Ed's experience and are inconsistent with the inspection fre-
quency for Bergen-Patterson and other brand suppressors established
by DL correspondence to several licensees following initial discovery
of this problem with Bergen-Patterson snubbers (example enclosed as
Enclosure 1).
In the case of Met Ed the snubbers involved have been
manufactured by Grinnell.
We recommend that the Technical Specifications for all licensees
should include inspections of snubbers at 120 day intervals.
l3
r
_ m _J
_ _ -
Et J. Brunner, Chief
R actor Operations Branch
Enclosure:
As stated
cc:
J. Davil
K. Seyfrit
F. Dreher
1Lylb (o '