ML20236K675
| ML20236K675 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/23/1998 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236K678 | List: |
| References | |
| NUDOCS 9807100040 | |
| Download: ML20236K675 (7) | |
Text
V
= - -
. - --.... -.; -- ;;. :: y - -
4 s
1 7590-01-P i
i UNITED STATES NUCLEAR REGULATORY COMMISSION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302 i
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO l
FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS 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 Florida Power Corporation (the licensee), for operation of Crystal River Unit 3, located in Citrus County, Florida.
The proposed amendment would allow operation with a number of indications previously L
identified as tube end anomalies (TEA) and multiple tube end anomalies (MEA) in the Crystal River Unit 3 (CR-3) Once Through Steam Generator (OTSG) tubes. The duration of the -
proposed license amendment would be until CR 3's next refueling outage, currently scheduled l
for fall 1999. This proposed change may be necessary due to the potential condition of i
i noncompliance with CR 3 Improved Technical Specification 5.6.2.10.4.b. Such a condition may j
result from confirmation of an ongoing re analysis of addy current testing (ECT) data, of indications previously identified as TEAS and MEAS in the upper roll expansion of the OTSG upper tube sheet, as now being within the pressure boundary of the tubes.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this l
l~
9807100040 900623 PDR ADOCK 05000302 f
P Pm
[
4.. r.,,y_ _.
~
= ~~
(_
5 X T;? -
T
=
,m 1
2 means that operation of the facility in accordance with the proposed amendment would not (1) l involve a significant increase in the probability or consequences of an accident previous.ly i
evaluated; or (2) create the poss!bility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by i
4 10 CFR 50.g1(a), the li.censee has provided its analysis of the issue of no significant hazards
)
consideration, which is presented below:
This change does not involve a significant hazards consideration for the following reasons:
j
)
\\
(1) involve a significant increase in the probability or consequences of an accident previously evaluated.
q This evaluation addresses the potential effects of operating with TEAS and MEAS j
within the pressure boundary cladding region. The indications remaining in service are within the upper end of the tube pressure boundary. Two accidents l
analyzed in the SAR [ safety analysis report] must be evaluated: Steam Generator j
Tube Rupture and Main Steam Line Break.
l The steam generator tube rupture accident assumptions bound the possible affects of leaving these indications in service. A complete circumferential severance of a tube is assumed in the accident scenario. The location of these j
indications in the upper tubesheet precludes a tube rupture from occurring (the j
tubes are restrained by the tubesheet). Additionally, in the event of a complete circumferential severance, the tube will not retract from the tubesheet. Thus, the probability of occurrence of this accident is not increased by leaving these indications in service.
1 The main steam line break accident is not initiated by the condition of the tubing.
However, an assumption of one gpm primary-to-secondary leakage through the OTSG is assumed in the MSLB [ main steam line break] accident analysis.
Calculated cumulative leakage, assuming all of the indications are leaking, is determined to be well below one gpm, thus the accident analysis initial assumptions bound the existing condition of the OTSGs. Thus,it is concluded that the probability of occurrence of a main steam line break is not increased by this change. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2)
Create the possibility of a new or different kind of accident from any accident previously evaluated.
n 1
i
... L ~ L~lG..= = =.
.=A T -
TI-- L - -
l l
i 3
l l
No new failure modes or accident scenarios are created by allowing operation with TEAS and MEAS extending within the tubes' pressure boundary. The TEAS and MEAS remaining in service are within the upper end of the tube pressure boundary and even in the event of a complete circumferential severance, the tube will not retract from the tubesheet. Therefore, the tubesheet hoop effect will still act to minimize leakage. The postulated potentialleakage generated from l
allowing these indications to remain in service is bounded by the CR-3 MSLB scenario. The MSLB scenario has been thoroughly evaluated and the potential damage to the steam generator tubes is not increased. This change does not increase the risk of a plant trip or challenge other safety systems Therefore, this change does not create a possibility of a new or different kind of accident from any previously evaluated.
(3)
Involve a significant reduction in a margin of safet/.
ITS Bases 3.4.12 contains relevant information pertaining to the limitations on RCS [ reactor coolant systemj leakage. These Bases discuss the one opm primary-to-secondary leakage assumed for a main steam line break accident as l
well as the steam generator tube rupture accident. As discussed, the maximum calculated accident leakage, assuming all of these indications leak, is well below one gpm. Therefore, the margin of safety as defined in the ITS bases is not significantly reduced.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.g2(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
i l
The Commission is seeking public comments on this proposed determination. Any comments received within 14 days after the e,:ste of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of the 14-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 dorating or shutdown of the facility, the Commission may issue the license amendment IL. ore the expiration of the 14 day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public snd State comments received.
i 4
8 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 a.ction will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rules and Directives Branch, l
Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commisalon, 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 6D59, Two White Flint North,11545 Rockville Pike, Rockville Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Copies of written 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 July 30, 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 whoss interest may be affected by this proceeding and who' wishes to participate as a partyin the l
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 Commission's " Rules of Practice for Domestic Licensing Proceedings"in 10 CFR Part 2.
Interested persons should co.clult a current copy of 10 CFR 2.714 which is available 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, Fiorida 34428. If a request for a hearing or petition for leave to intervene is l
filed by the above date, the Commission or an Atomic Safety and i.l;;ensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request s,nd/or petition; and the Secretary or the designated Atomic Safety and Ucensing Board willissue a not!ce of hearing or an appropriate order.
,.. = -
t
^,.,. _ _ = _ - -- - =...===..:- -..u 5
As required by 10 CFR 2.714, a petition fo, leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the procestilng. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) the nature of the petitioners right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioners property, financial, or other interest in the proceeding; and (3) the possMa effect of any order which may be entered in the proceeding on the petitioners 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 person 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 th's 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 oflaw or fact to be raised or controverted, in addition, the petitioner shall provide a br!af explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the centention and on
. which the petitionc intends to rely in proving the contention at the hearing. The petitioner must also provide references to those specific sources and documents of which the petitioner is aware l
and on which the petitioner intends to rely to establish inose facts or expert opinion. Petitioner
{
must provide sufficient information to shw inat a genuine dispute exists with the applicant on a materialissue oflaw or fact.' Contentions shall be limited to matters within the scope of the am6ndment under considuation. The contention must be one which, if proven, would entitle the i
1 I
I
... -m
. ~.,
- = - - - - - - - - - =
- _ =_ -
_, _,,m m.m.y.
t 6
petitioner to relief. A petitioner who fails to file such e supplement which satisfies these requirements with respect to at least one contention will not be permitted to particip:te as a Party.
Those permitted to intervone 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, inc'uding the opportunity to present evidence and cross-examins witnesses.,
If the amendrrient is issued before the expiration of the 30-day hearing period, the Commission will make a final determination on the issue of no significant hazards consideration.
If a hearing is requested, the final determination will serve to decide when the hearing is held.
~
1 If the final determination is that the amendment request involves no significant hazards I
consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearin0 Any hearing held would take place afterissuance of 1
the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary 1
of the Commission, U.S. Nuclear Regulatory Commission, Wachington, DC 20555-0001, l
Attention: Rulemakings and Adjudications Staff, or may be delivered to the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC, by the above date.
A copy of the petition should also be sent to the dffice of the Gencral Counsel, U.S. Nuclear
. Regulatory Commission, Washington, DC 20555-0001, and to R. Alexander Glenn, General Counsel, Florida Power Corporation, MAC - A5A, P. O. Box 14042, St. Petersburg, Florida 33733-4042, attomey for the licensee.
9 L
7 l
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for heanng will not be entertained absent a determination by the Commiss'on, tho' presiding officer or tha presiding Atomic Safety and Licensing Board that the l
petition and/or request should be granted based upon a balancing of the factors specified i
in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated June 18,1998, 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 doc Jment room, located at the Coastal Region Library, 8619 W. Crystal Street, Crystal River, 1
l Dated at Rockvills, Maryland, this 23rd day of June 1998.
I FO THE NUCLEAR REGULATORY COMMISSION l
onard A. Wiens, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation 1
i 4
l l
.