ML20236T303
| ML20236T303 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/24/1987 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236T299 | List: |
| References | |
| NUDOCS 8712010128 | |
| Download: ML20236T303 (9) | |
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l UNITED STATES NUCLEAR REGULATORY C0t! MISSION FLORIDA P0llER CORPOR.A.T.I.ON D_0,CKE,T NO. 50-302 NOTICE OF CONSIDERATION OF ISSUANCE OF AliENDl!ENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND'0PPORTUNITY FOR HEARIfiG The U.S. Nuclear Regulatory Commission (the Comission) is considering issuance of an amendment to facility Operating License No. DPR-72, issued to Florida Power Corporation (the licersee), for operation of the Crystal River Unit 3 Nuclear Generating Plant located in Citrus County, Florida.
The amendment would change the surveillance requirement for the emergency diesel generator loading to reflect the diesel generator ratings ard the present total load they would be expected to carry. In addition, the require-ment for verifying the auto-connected loads would be updated to reflect the present loads.
The amendment would be in response to the licensee's application for amendment dated October 26, 1987, as amended October 29, 1987 and November 16, 1987 and supplemented by the licensee's letter dated November 20, 1907. It was 4 requested that noticing of this amendment be treated as an exigency since insufficient time exists for the Commission's usual 30-day notice withcut Extending the current shutdown.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
8712010128 B71124 DR ADOCK0500g2 C_________________._____.____ _ _ _ _
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The Comission has made a proposed deterninaticri that the amendment request involves no significant hazards considerations. Under the Comission's reguia-tions in 10 CFR 50.92, this means that operation of the facility in accordance with the picposed amendment would not (1) involve a significant increase in the probability cr consequences of an accident previously evaluated; or (2) create the possibility of a new cr different kind of accident from any accident previously evaluated; or (3) invc1ve a significant reduction in a margin cf safety.
The emergency diesel generators are required to have sufficient capacity and capability to ensure that design conditions are not exceeded as a result of anticipated operational occurrences and that the core is cooled and contain-ment integrity and other vital functions are maintained in the event of postu-lated accidents. Upon a less of offsite pcwer at Crystal River l' nit 3, two automatic fast start diesel generators will supply power. These diesel gene-rators are sized so that either one can carry the required engineered safeguards leads. In order to ensure that this capability does not degrade, Technical Specification 4.8.1.1.2.d.4 established an 18-month surveillance requirement to test to greater than or equal to 3000 kw fcr greater than or equal to 60 minuter.
The actual test load (approximately 3100 kw) was within the 30 minute rating (3001 to 3300 kw) of the diesel, but slightly lower than the highest calcu-lated accident load of 3180 kw.
Since establishment of the TS surveillance requirement, other loads have beer, added to the emergency diesel generators and a more accurate load arelysis l has beer. performed. These factors have resulted in the "A" emergency diesel generatcr being required to operate at a slightly higher load (3248 kw), still l l
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within its 30 minute rating, in two low-probability. accident scenarios. In ,
both these scenarios, the largest load on the diesel generators, the energency feedwater pump (EFV), will start but is not required for accident fritigetier ard will be er.anually tripped, bringing the accident _ load on the diesel genera-tors within the POOC-hour rating (2750-3000 kw). Previously, the EFV pump was tripped autoriatically after 30 minutes. All other accident scenarios result ir.
1 cads within the P000-hour rating of the diesel _ generators. The diesel generater manufacturer has indicated that the 30 minute rating is cuniulative. Frior to continued engine operation, after engine operation in the 3001 kw to 3300 kw range for 30 minutes of total accumulated tirne, the engines must be disasstr-bled and a special inspection made supplemental to the 18-month inspectier currently required by Technical Specifications.
In order to reflect current 1cadings to ensure the diesel generators are
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capable of carrying their required engineered safeguards loads during the worst ,
case loading condition, and to resolve the conflict between the inspection requirement and the surveillance requirement, the surveillance requirement is being mcdified to require that 5 minutes of this test will be performed in the 30 minute rating (3248 kW) and the remaining 55 minutes of the test will be performed in the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating (between 2750 and 3000 kw).
In addition, TS 4.8.1.1.P.d.5 is being updated to require verificaticr.
that the auto-connected loads do not exceed the revised highest calculated accident load (3248 kw).
The licensee has corr.itted to develop a long-range plan for increasing diesel generator loading margins by reducing loads further or incrn sing onsite AC power sources, and anticipates resolution by the end of the next scheduled refueling outage, i
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The change to tht ;Wiesel,graerator loading is being made to accurately ,
I reflect the' engineered safeguards load cordition on the diese1 gereratcrs. -
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, Testing at thest loads for 5 minutes and at the 7000 hour0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> rating fer 55 triretcr.
J i will provide assurance'that the diesel generators are capable of supplying their required engineered efeguards leads, while remaining capable of supply-
,. ing the required engineered safeguards loads for the length of the fuel cycle.
Cased on the above, this change will not: ,
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- 1. Inyc1ve a significant increase in the probability cr consequences of an p.
a accident previously evaluated because the surveillance requirements fcr diesel generator loading will new accurately reflect the worst case lead- j ing ccodition on the diesel generefor. As a result, testing at these
, loads will provide assurance that the diesel generators are capahle of supplying their required engineered safeguards loads.
- 2. Create the possibility cf a new or different kind of accident from any
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accident previously evaluated because the proposed change to the Technical
, Specification introduces no new rnode of plant cperation not does it require physical modification.
- 3. Involve a significant reduction in a :nargin of safety. /,1though the l maximuni diesel generator load of 3248 kw is slightly higher, it is still within the 30 minute rating and does not result in a significant reduction in the diesel generator margin of safety. Since the proposed ;
change accurately reflects the worst case loading condition on the diesel generaters; testing at these loads and at the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating in the manner described above will previde greater assurance that the diesel generators are capable of supplying their required engineered safeguards loads, while remaining capable of supplying these loads for the lenyth of
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w the fuel cycle. A major load which would not be required in the scenario which causes the maximum diesel generator load will be tripped, thereby bringing the load to within the F000 hour rating. In addition, the licensee has cortdtted to take action by the end of the next scheduled refueling cutage to increase diesel generator margins.
Accordingly, the Commission proposes to determine that this change does not involve significant hazards considerations.
The Conodssion is seeking public concients on this proposed determinaticr.
Any conments received within 15 days after the date of publication of this notice will be considered in making any final determination. The Commission will not normally make a final determination unless it receives a request for a hearirg.
Written comments may be submitted by mail to the Rules and Procedures Branch, Division of Rules and Records, Office of Adndnistration and Resources Managenent, U. S. Nuclear Regulatory Commission, Washington, D.C. 70555, and shculd cite th publication date and page nuniber of the FEDERAL REGISTER notice.
Written comments may also be delivered to Room 4000, Maryland National Bank Building, 7735 Old Georgetown Road, Bethesda, Maryland from 8:15 a.n. to 5:00 p.m. Copies of written comnents received may be examined at the NRC Public Document Room, 1717 H Street, NW, Washington, D.C. The filing of requests for hearing and petitions for leave to intervene is discussed below.
By December 14, 1987, the licensee mey file a request for a hearing with respect to issuance of the anendnent to the subject facility cperating license and any person whose interest may be affected by this proceed-ing and who wishes to participate as a party in the proceeding must file a 4
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written petition for leave to intervene. Requests for a hearing and petitions sfer leave to intervene shal[1;Ne filed in accordarce with the Comission's s ,
.." Rules of Practice for Donntic Licer. sing Pro'ceedingF irr 10 CFR Part 2. If a request fer's hearing or petit'on ;[cr leave to inter er.e is filed by the abcVe date, the Corrission or an Atomic Safety and Licinsing Board, desigrated by the n 'n g', h - (3 gccidssion or bywthd thairman of the Atorr.icTafety and Licensing Board Panel, .
'N will\ rule on the requert and/or petition; and the Secretary or the designated Att11cSafetyandLicensingBcirdwillissueanoticeof'hearingoranappro-priate order.
As reovired by 10 CFR 2.714, a petition for leave to intervene shall set fcrthwithpartidularitytheir.terestofthepetitiererintheproceeding,and y hoh that intehest my be affected tiy the remits [of the proceeding. The petitiop n" ' Mould specifically explain , the rea, sonsu why intervention should be permitted with
'f< partico?ar reference to'the following factors: (1) the nature of the petitioner's rpghtundertJe'Acttobemadeapartytotheproceeding;(2)thenatureand
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edent of the pe;t itioner's proper ~ty,' fir.ar.cial, or' other interest in the y
prc,ceeding; and (3) the possible effect of any order which may be entered in the
@.sceedingonthepetitioner'sinterest. The petition should also idertify the
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specificaspect}s)ofth'esubjectmatteroftheproceedingastowhich t
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petitio,ner wishes to intervene. Any person who has filed a petition for leave
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to intervene or#. c has
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beerf admitted as 6 party may amend the petition without a requestingleaver0(theBoarduptofifteen(15)dayspriortothefirstpre-hearing confe'rt1)cd scheduled in the proceeding, but such an amended petition must satisfy the specif8 city requirements described above.
q L flot la'.y than' fifteen (15) deys prior to the first prehearing conference "
scheduled in the proceeding, a petitioner shall file a supplement to the petition t
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7-to intervene, which must include a list of the contentions that are sought to be litigated ir, the matter, and thc bases for each conter. tion set forth with reason-
-able specificity. Contentions shall be limited.to matters within the scope of the an+ndrent under consideration. A petitioner who fails to file such a supple-ment which satisfies these requireraents with respect to at least one contentior, will not be pertiitted to participate as a party.
These permitted. to intervene becone parties tc 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 crcss-examire witnesses.
If.a hearing is requested, the Commissicn will make a final determination en the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
If the final deterniination is that the amendnent request involves ne
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sigr.ificant hazards considerations, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendrent.
If the final deterniination is that the amendment request involves sicrifi-car.t hazards considerations, any hearing held would take place before the issuarce of any amendment.
Ferme11y, the Commission will r.ct issue the anendrer.t until the expiration of the 1E-day r.otice period. However, should circuristances change during the notice period, such that failure to act in a tinely way would result, fcr exarple, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 15-day notice period, provided that its
w final determination is that the amendrent involves no significant hazards con-sideration. The final determination will consider all public and State correrts received.
Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance. The Cor.-
missier expects that the need to take this action will occur very infrequently.
A request for a hearirig or a petition for leave to intervene must be filed with the Secretary of the Conrission, U.S. Nuclear Regulatory Comissien, Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Corrission's Public Document Room,1717 H Street, N.P.
i Washington, D.C., by the above date. Uhere petitiens are filed during the last ten ('C) days of the notice period, it is requested that the petitioner i
promptly so inforr the Commission by a toll-free telephone call to l'esterr Union at (800) 225-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following messege addressed to Nerbert N. Berkow: petitioner's name and telephore nunber; date petition was mailed; plant nane; and publication date and page number of this j
TE0ERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washingten.
D.C.
20555, and to R. W. Neiser, Senior Vice President and General Ccunsel, Florida Power Corporation, P.O. Box 14042, St. Petersburg, Florida 33723.
Ncrtimely filings of petitions for leave to intervene, anended petitior.s, 1 supplemental petiticos and/or requests for hearirs will not be entertained absent a deterraination by the Comission, the presiding officer or the presiding Atomic i Safety and Licensing Board that the petition and/or request should be granted based upon a balar.cing of the factors specified in 1C CFR 2.714(a)(1)(i)-(v) and 2.714(d).
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For further details with respect to this action, see the applicaticri for amendo.ent dated October 26, 1987, as amended October 29, 1987 and. November 16, 1967 and supplemented November 20, 1987, which are available for public inspection at the Commission's Public Cocunent Room, 1717 H Street, N.W.,
Washinrton, D. C. 20555, and at the Local Public Document Room, Crystal River Library; 668 N.W., First Avenue, Crystal River, Florida 326?9.
Cated at Bethesda, Maryland, this 24th day of November,1987.
FORTHENU{LEARREGULATORYCOMMISSION 3-
,' _ N/t arle > Silver, Project l'anager Proje Directorate II-2 Civision of Reactor Projects I/II Office of Nuclear Reactor Regulation l
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