ML20245L138
| ML20245L138 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/28/1989 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Sylvia B DETROIT EDISON CO. |
| Shared Package | |
| ML20245L140 | List: |
| References | |
| NUDOCS 8905050291 | |
| Download: ML20245L138 (1) | |
See also: IR 05000341/1989007
Text
_ _ _ _ _ _ _ _ - - . - _ - - - _ _ _ . - _ - - -. . _ _ _ - -
- . - - - -
-
---
- - - - - - - - -
- - - - - - - - -
- - - - - - - - -
-
'
'M
-
b
/
-
1 Electnc
POWER COMPANY
+
231 W. Mictugon, RO. Box 2046. Milwaukee, WI 53201
(414) 221-2346
VPNPD-8 9-2 53
URC-8 9-0 50
April 26, 1989
Document Control Desk
U.S. NUCLEAR REGULATORY COMMISSION
Mail Station P1-137
D.C.
20555
' Gentlemen:
DOCKETS 50-266 AND 50-301
TECHNICAL SPECIFICATION CHANGE REQUEST 133
OVERPRESSURE MITIGATING SYSTEM OPERATION REPORTING REQUIREMENTS-
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
In accordance with the requirements of 10 CFR 50.59(c), 50.90,
and 50.4, Wisconsin Electric Power Company (Licensee) hereby
requests amendments to Facility Operating Licenses DPR-24 and
'DPR-27 for Point Beach Nuclear Plant Units 1 and 2,
respectively,
to incorporate changes in the plant Technical Specifications.
These proposed changes, as detailed below, clarify the reporting
requirements for operation of the Overpressure Mitigating System
(OMS) and delete two schedular commitments which have been
implemented.
Specification 15.6.9.2.C,
" Overpressure Mitigating System Opera-
tion," requires a special report to be submitted to the NRC within
30 days of an event which, by licensee's evaluation, could have
resulted in an overpressurization incident had the overpressure
mitigating system not been operable.
This specification had been
interpreted to apply only to actuation of the pressurizer power
operated relief valves (PORVs) in the low temperature overpressure
protection (LTOP) mode.
As a result of an event reported in our
letter to the Commission dated February 9,
1989, it was recognized
that the NRC Safety Evaluation Report (SER), dated May 20, 1980,
which accompanied the approval of Specification 15.6.9.2.C,
directed that this special report be submitted not only for PORV
LTOP operation but also for actuation of the residual heat removal
(RHR) system relief valves if such actuation would have mitigated
an.overpressurization incident.
The SER also recognized the RHR
system relief valves as a diverse relief system at Point Beach
because the RHR system is not automatically isolated during a
pressure transient.
Accordingly, we have propoced this revision
to the specification to provide assurance that operation of either
,
I
the PORVs in the LTOP mode or the RHR system relief valves ar
^O)1
6
reported as required.
q
9905060291 890426
~
l
}
DR
ADOCK 05000266
p
.4saWhwonthwasinherryCorpwhn
\\
_ _
- - - _ .
____ _ - -
.
~
NRC Document Control Desk
.
April 26, 1989
.
Page 2
Additionally we propose the removal of two schedular commitments
contained in the footnotes of two tables.
The first is contained
in Table 15.3.5-1 (page 2 of 2) as related to the setting limit
for Item 10, " Loss of Voltage."
The associated relays have been
installed as required and the footnote is no longer appropriate.
The second is in regards to Item 7.1,
" Oxygen Monitor," in Table
15.7.4-2.
The oxygen monitor was installed as required and the
footnote is no longer appropriate.
As required by 10 CFR 50.91(a), we have evaluated these proposed
changes in accordance with the standards specified in 10 CFR 50.92
to determine if the proposed changes constitute a significant
hazards consideration.
A proposed license amendment involves no
significant hazards consideration if operation of the facility in
accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequence of
a.. acci-
dent previously evaluated, (2) create the possibility of a new or
different kind of accident from any accident previously evaluated,
or (3) involve a significant reduction in a margin of safety.
These proposed changes are strictly administrative in nature and
involve no physical plant modifications and no changes in plant
operations or procedures.
Therefore, these proposed changes would
not violate any of the three criteria and we have determined that
the proposed amendments will not result in a significant hazards
consideration.
Please contact us if you have any questions concerning this
request.
Very truly yours,
,,fj.T -
C.
W.
Fay
Vice President
Nuclear Power
Enclosures
Copies to NRC Regional Administrator, Region III
l
NRC Resident Inspector
R.
S. Cullen, PSCW
i
_____._m._-_-._
. _
_ _ _