ML20198M799
| ML20198M799 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/09/1998 |
| From: | Raghavan L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198M804 | List: |
| References | |
| NUDOCS 9801200128 | |
| Download: ML20198M799 (8) | |
Text
,
y
?. t 7590-01-P
~
UNITERSTATES NUCI FAR REGULATORY COMMISSION.
FLORIDA POWER CORPORATION B
DOCKET h)O. 50-302 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARD 3 CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of -
an amendment to Facility Operating License No. DPR 72, issued to the Florida Power Corporation (FPC or the licensee), for operation of the Crystal River Nuclear Generating Unit 3 (CR3) located in Citrus County,' Flodda.
.The licensee propot&d a revision to the description of the starting logic for the Reactor Building (RB) Recirculation System Fan Coolers, as discussed in the CR3 Final Safety Analysis Report (FSAR), Chapters 5,6,7 and 9, and improved Technical Speci'ication (ITS) Bases Section 3.6 The change 11 #e starting logic would ensure that only one RB Fan starts on an Engineered Safeguards (ES) Reactor Building isolation and Cooling (RBIC) signal. A modification to th9 plant will install components that could increase the probability of occurrence of a malfunction of equipment impMant to safety previously evaluated in the FSAR. FPC uas determined that proposed changes to associated electrical controls involve an Unreviewer Safety Question (USQ). %ere, fore, NRC review and approval are required.
1
- Before issuance of the propoaed license amendment, the Commission will have made
- fndings mquired by the Atomic Energy Act of 1954, as amended (tne Act) and the kf
' _ Commission's regulations.
The Commission has made a proposed de.ermination that the amendment request 9901200128 990109 I
PDR.ADOCK 05000302 l
P PDR j.
t:
j i
2 involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new o.' different kind of j
accident from any accident previously evaluated; or (3) involve a significant reduction in a i
margin of safety. The licensee made its request on December 5,1997, and as required by 10 CFR 50.91(a), and provided its analypis of the issue of no significant hazards consideration which is presented below:
1.
Does not involve a significar.1 increase in the probability or consequences of an accident previously evaluated.
The change to the starting logic for the RB Fans affects the ES equipment that responds to mitigate an accident. The RB Fans are not accident initiators and the change to the starting logic cannot initiate an accident. Therefore, the probability of occurrence of an evaluated accident is not increased.
?
The RB Fan start logic change selects an available RB Fan to run upon an RBlC actuation, but only allows the operation of one RB Fan to prevent overloading the w
SW [ Nuclear Services Closed Cycle Cooling) System. The containment analysis for CR-3 assumes that one train of ES equipment is available for accident mitigation, specifically, one RB Fan and one RB Spray train for containment cooling. The combination of two RB Spray trains with no RB Fans is also if evaluated and found to be acceptable. These availab'e containment cooling equipment combinations represent the minimum that would be available for acddent response both before and after the imolementation of this change, in addition to the same equipment being available to mitigate an accident, there is no change to the analyzed containment response. The tin:e delay in the start of an RB Fan of up to several seconds due to the modification has been svaluated through containment analysis sensitivity studies. The results of these studies show that containment peak pressure and temperatere, and long term temperature profiles, are not affected. The consequences of an accident are directly related to containment pressure and temperature conditions. Since containment conditions following an accident are not affected by this modification, there will be no change to the consequences of any analyzed accident.
-: 2.
Does not create the possibility of a new or different kind of accident from any accident previously evaluated.
1
l.
i.
3 The _ modification changes thh RB pan start logic in the event of an accident. The '
new start circuit ensures that one RB Fan is opers, ting in response to an RBIC actuation, but prevents the operation of two fans. This modification prevents the 3ermal overloading of the SW System in_ order to preserve the operability of i
equipment cooled by the SW System. Several potential new tailure modes were
- evaluated and determined not to create the possibility of a new or different kind '
of accident.
Additionaliy, the RB Fans are engineered safeguards equipment designed to mitigate on accsdent, and the SW System is an accident mitigation support.
system. These systems are not accident initiators. The ES electrical busses 3
and the EDG [ emergency diesel generator] are not affected by this change. All l_
containment design conditions are met with this change.'
Therefore, this change cannot create the possibility of an accident of a different kind than previously evaluated in the SAR.
3.
Does not involve a significant reduction in the margin of safety.
m' Technical Specification 3.6.6 states that two RB Spray trains and two RB containment cooling trains must be aperable. This specification ensures diversity and redundancy of the containment cooling system. Follow ng the i
modification, all margins will be maintained. Two RB Fans will be operable and capable of starting on an RBIC signal. The modified circuitry meintains the RB Fan redunda'ncy. The RB Sprays are not affected by this modification.
The margin of safety associated with the containment maximum pressure and ten ',,ture in response to a LOCA [ loss-of-coolant accident] is not affected since any failure of this modification results in equipment combinations that have I
been analyzed and determined to be acceptable. Containmant LOCA response sensitivity studies have verified that the small start delay, associated with the
}
modified RB Fan start circuit, has no effect on the post LOCA peak temperature and pressure in containment. Also, the failure of SW valves that resuits in the loss of the ability of tb P9 Fan Coolers to remove heat or the failure of either RB Fan to run, will not affect the containment peak temperature and pressure
[
conditions since two trains of RB Spray are available.
I The proposed modification allows only one RB Fan to operate post-accident.
(
This ensures that the SW System is not overloaded and SW temperatures remain within design basis limits. Therefore, there is no reduction in the margin of safety.for the SW System equipment cooling function after the implementation of this change.
The small additional electrical loads, and the out-of-sequence loading of an RB Fan associated with this change have been evaluated and determined to be
' within the load limits of the EDG and ES electrical busses. Therefore, there is no reduction in the electrical system margin of safety.
=
=
4 Based on the above evaluation, there is no reduction in the margin of safety associated with the equipment and systems affected by this change.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards
- .onsideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considerer' in making any final determination.
Normally, the Commission will not issue the ameridment antil the expiration of the 30-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the ameWment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the FEDERAL. REGISTER a notice of issuance. The Commission expects that the need to take this action will occur very 1
hfrequently.
Written comments may be submitted by mail to the Chief, Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of
- Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6D22, Two White Flint North,11545 Roc,<ville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Copies of written
5
. comments received may be examined at the NRC Public Document Room, the Gelman -
- Building; 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By Feb.17,1998, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose -
interes,t may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene.
- Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commir.sion's Rules of Practice for Domestic Licensing Proceedings"in 10 CFR Part 2.
1
' interested persons should consult a current copy of 10 CFR 2.714 which is availa~cle at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC, and at the local public document room located at the Coastal Region Library, 8619 W.
Crystal Street, Crystal River, Florida.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the decretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set fodh with particularity the interest of the petitioner in the proceeding, and how that interest may be af'ected by the rsaults of the proceeding. The petition should specifically explain the reasons
- why latervention should be permitted with particu!ar reference to the following factors
- (1) the
. nature of the petitioners righ't under the Act to be made a party to the proceeding; (2) the K nature and extent of the petitioners property, financial, or rther interest in the prcceeding; and
k 3.-.
E.,7 6
- (3) the possiole effect of any order which may be entered in the proceeding on the petitioner's
. interest. The' petition should also identify the specific' aspect (s) of the subject matter of the -
proceeding as to which petitioner wishes to intervene. Any pomon who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without
. requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must-include a list of the contentions which are sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In
. addition, the petitioner sha'i provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the coniention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner most also provide references to those specific sources and documents of which the petitioner is I
1 aware and on which the petitioner intends to rely to establish those facts or expert opinion.
Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Comentions shall be limited to matters within the scope of the amendment under consideration, The contention must be one which, if proven, would erele the petitioner to relief. A petitioner who faile to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to porticipate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully.
in the conduct of the hearing, including the opportunity to present evidence and cross-examine
i
^
7 witnesses.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
If the final determination is that the amendn:ent request involves no significant hazards, consideration, the Commission may issue the amendment and make it immediately effective, notwithttanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that tne amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A mquest for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff may be delivered to the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washin] ton, DC, by the above date. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washingtcn, DC 20555-0001, and to R. Alexander Glenn, General C8unsel, Florida Power Corporation, MAC - ASA, P. O. Box 14042, St.
Petersburg,' Florida 33733-4042, attorney for the licensee.
Nontimely filings of petitions for leave to intervena, amended petitions, supplemental petitions ond/or requests for hearing will not be entertained absent a determination by the
[
Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specifed in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this P. an, see the application for amendment dated
i 4
8-December 5,1997, which is available for public inspection at the Commission's Public -
Document Room, the Gelman Building,2120 L Street, NW ~, Washington, DC, and at the local public document room, located at the CoastLI Region Libiary, 8619 W. Crystal Street, Crystal River, Florida.
Dated at Rockville, Maryland, this 9th day of January 1998.
FOR THE NUCLEAR REGULATORY COMMISSION d
L. Raghavaq, Senior Project Manager Project Directorate ll-3 Division of Reactor Projectr. - 1/11 Office of Nuclear Reactor Regulation i
.t 6
_ _ _ _ _ _ _ _ - _ _ _ - - - _ - - _ _.