ML20127A734
| ML20127A734 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crystal River |
| Issue date: | 07/06/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Clark K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20127A737 | List:
|
| References | |
| FOIA-84-794 NUDOCS 8307150010 | |
| Download: ML20127A734 (5) | |
Text
e AP Efco
'o, -
UNITED STATES
.}
I
'l!
. f) %
NUCLEAR REGULATORY COMMISSION
'J WASHINGTON, D. C. 20555
{4
?[.. /.
JULY 6 1983 So R O 2-MEMORANDUM FOR:
Kenneth M. Clark Public Affairs Officer Region II FROM:
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
SUBJECT:
PROPOSED PRESS RELEASE Attached is a proposed press release relating to an application for an amendment to the operating license for the Crystal River Unit 3 Nuclear Generating Plant dated June 24, 1983.
Because of exigent circumstances, time does not allow for normal publication in the FEDERAL REGISTER.
It is requested that this announcement be released as soon as possible to the media in the area of the facility and that a copy be sent to the State official and licensee.
Jo n F. Stolz, Chie erating Reactors Branch #4 ivision of Licensing
Attachment:
Proposed Press Release cc w/ attachment:
JFouchard Glainas RHernan DEisenhut OELD RTifgiam HDenton 4
i n p31SML g
4 i
PRESS RELEASE The Nuclear Regulatory Commission has received an application dated June 24,1983, from Florida Power Corporation (on behalf of eleven other member utilities) for an amendment to the operating license for the Crystal River Unit 3 Nuclear Generating Plant located in Citrus County, Florida.
If approved, the amendment would allow the utility the option to utilize a small number of roving fire patrol personnel to check certain plant areas for fires on an hourly basis in 1.ieu of approximately 50 extra personnel presently monitoring these areas on a stationary continuous basis. The use of roving fire patrol would also require operable fire detectors in each area. Florida Power Corporation has requested NRC action on its request as soon as possible.
Following an initial review of this application, the NRC has made proposed 4
(preliminary) detennination that the requested arnendment does not involve a significant~ hazard consideration.
Under NRC regulations, this means that the proposed amendment does not involve a significant increase in the probability or consequences of an accident, would not create the possibility of a new or different kind of accident, or involve a significant reduction in a safety margin.
On June 14, 1983, Florida Power Corporation discovered that a large number of fire dampers in various building ventilation systems have not been certified by the manufacturer to be able to sustain a fire for a 3-hour period.
The devices are only certified for a l 1/2-hour rating.
NRC regulations require such devices to be certified with a 3-hour rating.
Consequently, Florida Power
~
Corporation has considered the subject dampers to be non-functional and, as required by the current Crystal River Unit 3 Technical Specifications, is required to maintain a continuous fire watch at each damper,
l
.I
)
l The Commission has provided guidance concerning decision as to whether j
l an amendment involves NSHC by providing certain examples.- One.of the examples of actions considered not likely to involve significant hazards considerations is a change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan, or equivalent.
The amendment is only a minor change from the present Technical
- Specifications to the Standard Technical Specifications. The change discussed herein constitutes a change of the Crystal River Unit 3 Technical Specifications to agree with the corresponding section of the Standard Technical Specifications approved by the NRC for reactor plants designed by Babcock and Wilcox (published as NUREG-0103, Revision 4 dated Fall 1980).
The Crystal River reactor plant is.of Babcock and Wilcox design. The current Technical Specif.ications for the Crystal River facility were approved in February 1978 and were based upon a previous revision of the Standard Technical Specifications. At that time, no consideration was given for the existence of installed fire detection systems for those plants which had them, and the only mitigative action approved for non-functional fire barrier components was establishment of a continuous fire watch.
Subsequently, the NRC revised the Standard Technical Specifications to allow the option of a roving fire watch in lieu of a continuous fire watch provided a fire detection system on at least one side of the affected fire barrier is installed and operable.
The nature of this change is to allow reliance upon installed fire detection devi ces, which are a part of the NRC-approved fire protection system, for continuous fire protection,and to provide backup fire detection capabilities by use of visual observation in each space on a once-per-hour basis by a fire watch. Since the
A
.i.
fi re dampers in. quest'iob 'have be,en.'carti.fied to.be able to wit'h' stand
~
~
~
f.,fi re for at least 1-T/2. liours, allowance of this _gstion.is considered by.
.,the NRC as pEnvidino adeguate fire. protection..
On the basis discussed
~
above, the Commission proposes to determine that the proposed amendment does not involve a significant hazards consideration.
The Commission has detennined that due to unusual circumstances, there is no time to publish its usual notice in the FEDERAL REGISTER for public comment regarding the proposed action prior to taking the action. The unusual circumstances result from the fact that Florida Power Corporation, due to an unforeseen deviation in fire dampers as they were installed in the facility in the late 1970's, is currently required by the NRC-approved Technical Specifi-cations for operation of the facility to employ a large number of extra personnel.
The licensee considers the resultant cost to be excessive and the NRC considers that the present requirement can be relaxed without jeopardizing public health and safety.
If the initial determination becomes final, the NRC will -issue the amendment l
l without first offering an opportunity for a public hearing.
An opportunity for a hearing will be published in the FEDERAL REGISTER at a later date-and any hearing request will not delay the effective date of the amendment.
l If the NRC decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for 1
a ' prior hearing will be published in the FEDERAL REGISTER and, if a hearing I
is granted, it will be held before the amendment is issued.
l l
O
- i
_4 Comments on the proposed detemination may be telephoned to Mr. John F.
Stolz, Chief of Operating Reactors Branch No. 4, by collect call to (301) 492-8960.
All comments received by July 18, 1983, will be considered in reaching a final detemination. A copy of the application may be examined at the NRC's local public document room located at the Crystal River Public Library, 668 N.W. First Avenue, Crystal River, Florida.
i e
e 5
e 4
.. ~,
, - -