ML19354D718
| ML19354D718 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/19/1989 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Saporito T AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 9001020027 | |
| Download: ML19354D718 (2) | |
Text
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C December 19, 1989 DISTRIBUTION
-DocketeFile(50-302)
DMiller i
NRC & Local PDRs BSinkule, RII SVarga Mr. Thomas J. Saporito Glainas 1202 Sioux Street HBerkow Jupiter, Florida 33458 OGC (for info. only)
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Dear Mr. Saporito:
HSilver L
This is in response to your corsnents dated October 27, 1989 and entitled "Public Comnents to Federal Register Notice 40221 Vol. 54 No.188" concerning the amendment request by Florida Power Corporation to allow a one-tine delay of the 18-month diesel generator full. load test at Crystal Rivcr Unit 3 until the next refueling outage, currently scheduled for the spring of 1990. Notice of this proposed amendment was published in the Federal Register on September 29, 1989 (54 FR 40221) and stated t1at any public conunents received "within 15 days af ter the date of publication of this notice will be considered in making any h
final determination." Since the amendment was noticed on an exigent basis, a k
final determination of no significant hazards consideration was made. Amendment No.123 concerning this matter was issued on October 17, 1989.
Your consrents were not received during the 15-day consnent period as stated in the notice, or before issuance of the amendment, and therefore were not considered in making the final determination. However, the staff's evaluation of the proposed change contained in the Safety Evaluation supporting the amendment addressed the concerns contained in your concents.
For your information, a copy of Amendment No. 123 is enclosed.
Sincerely,
/s/
Harley Silver, Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
_ Amendment 'k.
123 cc w/ enclosure:
S:. next page 6f7)
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DATE : 12/ k /89
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- 12/ /89 OFFICIAL RECORD COPY Document Name:
SAPORITO LETTER Ofol
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9001020027 891219 ADOCK0500gCp, PDR P
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Thomas J. Saporito Crystal River Unit No. 3 Nuclear Florida Power Corporation Generatir.g Plant ec*
Mr. A. H. Stephens State Planning and Development General Counsel Clearinghouse Florida Power Corporation Office of Planning and Budget MAC - A50 Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee, Director Chairman Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219-NA-2C 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 32650 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director Babcock & Wilcox Nuclear Operations Site Support Nuclear Power Generation Division Florida Power Corporation 1700 Rockville Pike, Suite 525 P.O. Box 219-NA-21 Rockville, Maryland 20852 Crystal River, Florida 32629 Senior Resident Inspector Mr. Gary L. Boldt Crystal River Unit 3 Vice President, Nuclear Production U.S. Nuclear Regulatory Comission Florida Power Corporation 15760 West Powerline Street P. O. Box 219-SA-2C Crystal River, Florida 32629 Crystal River, Florida 32629 Regional Administrator, Region 11 Mr. Percy M. Beard, Jr.
U.S. Nuclear Regulatory Commission Senior Vice President,
~ 101 Marietta Street N.W., Stite 2900 Nuclear Operations Atlanta, Georgia 30323 Florida Power Corporation ATTN: Manager, Nuclear Operations Mr. Jacob Daniel Nash Licensing Office of Radiation Control P.O. Box 219-NA-21 Departnent of Health and Crystal River, Florida 32629-Rehabilitative Services 1317 Winewocd Blvd.
Tallahassee, Florida 32399-0700 Acministrator Department of Environmental Regulation Power Plant Siting Section
' State of Florida 2600 Blair Stone Road Tallahasiee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florire 32304
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ENCLOSURE-Oc tobe r 17, 1989 Docket No. 50-302 Mr. W. S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN: -Manager, Nuclear Licensing P. O. Box'219 Crystal River, Florida 32629
Dear Mr. Hilgus:
SUBJECT:
CRYSTAL RIVER UNIT 3 - ISSUANCE OF AMENDMENT (TAC NO. 74163 )
The Cosmissior.= has issued the enclosed Amendment No.123 to Facility Operating
-License No. CPR-72 for the Crystal River Unit No. 3 Nuclear Generating Plant (CR-3).
This: amendment consists of changes to the Technical Specifications
'(TSs) in respcnse to your application cated August 9,1989.
This amendment extends, on a cr.e-time basis, the surveillance interval for the-emergency diesel gar. orator full load test until Refuel 7, currently scheduled to start in March,1990.
- A copy of the safety Svaluation is also enclosed. The Notice of Issuance will be incluced in the Comission's biweekly Federal Register notice.
Sincerely,
Original signed by Harley Silver, Project Manager Project. Directorate II-2 Division of Reactor Projects - 1/II Office of huclear Reactor Reguistion Enclosurta:
1.
Amendment No.123 to DPR-72 2.
Safety Evaluation cc w/ enclosures:
See next page 1
QN0Y f
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'o Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. A. H. Stephens State Planning and Cevelopment General Counsel Clearinghouse Florida Power Corporation Office of Planning and Budget MAC - ASD Executive Of fice of the Governor P. O. Box 14L42 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Floride 32301 Mr. P. F. McKee, Director Chairman Nuclear Plant Operations Board of County Commissioners Ficrida Power Corporation Citrus County P. O. Box 219-NA-2C 110 North Apopka Avenue Crystal River, Florida 32629 Inverness Florida 32650 Mr. Robert D. Borsum Mr. Rolf C. Widell, Director Babcock & Wilcox Nuclear Operations Site Support Nuclear Power Generation Division Florida Power Corporation 1700 Rockville Pike, Suite 525 P.O. Box 219-NA-21 Rockville, Maryland 20852 Crystal River, Florida 32629 Senior Resioent Inspector Mr. Gary L. Boldt
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Crystal River Unit 3 Vice President, Nuclear Production U.S. Nuclear Regulatory Commission Florida Power Corporation 15760 West Pcwerline Street P. O. Box 219-SA-2C Crystal River, Florida 32629 Crystal River, Florida 32629 Regional Aon.inistrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehebilitative Services 1317 Winewood Blvd.
T411ahassee, Florida 32399-0700 Administrator 1
Dsportment of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tal16hassee, Florida 32301 Attorney General Department of Legal Aff airs The Capitol Tallahassee, Florida 32304
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UNITED sfATES E
NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20$$5
- .g-FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAlhE5VILLE CITY OF KISSIMMEE CITY OF LEE 55URG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION. CITY C CITY OF OCALA ORLA!00 UTILITIES C0mI55L0h AhD CITY OF CRLANDO S EBRING UTILITIli5 00fMI55 ION SEMTlIUU. ELECTRIC COOPERATIVE. JNC.
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s.b UNIT 3 NUCLEAR __ GENERATING PLANT
.ciENDME.! fi' ' A':!LITY ~~ 'ERATING LICENSE 5
Amenenent No.123 License No. CPR-72 1.
The Nuclear Regulatory Comission (the Commission) has found that-A.
The application for emendment by Florida Power Corporation, et al.
(the -licensees) dated August 9,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the' Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
)
'D.
The issuance of this amendment will-not be inimical to the comon c=fense and security or tu the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-72 is hereby amenced to read as follows:
Technical Specifications The Technical Specifications containen in Appendices A and B, as revised through Arendment No.123, are hereby incorporated in the lictnse. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This licena amendment is effective as of its date of issuance.
1 FOR TH NUCLEAR REGULATORY COMMISSION I
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Fe art fl. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Offica of huclear Reactor Regulation
Attachment:
' Changes to the Technical Specifications Date of 1ssuance: October 17, 1989 e
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ATTACHMENT TO LICENSE AMENDMENT NO.123 FACILITY OPERATING LICENSE NO. CPR-72 DOCKET NO. 50-302 Replace the folitwing pages of the Appendix "A" Technical 5pecifications with the attached pages.
The reviseo pages are identified by amenon.ent number and contain vertical lines indicating the area of changa.
The corresponoing overleaf pages are also provided to maintain accurent completeness.
Removt insert 3/4 8-5 3/4 8-5 3/4 8-6c 3/4 8-6c l
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EttcTRicAL POWER SYSTDt1 SURVEli. LANCE REQUIREMENTS (Continued) 2.
Verifying the generator capability to reject a load of 1515 kw without tripping.
- 3.
Simulating a loss of offsite power in conjunction with Reactor Building high pressure and Reactor Building high high pressure tests signals, and; a)
Verifying de energization of the emergency buses and load shedding from the emergency busses, b)
Verifying that the 4160 v. emergency bus tie breakers open, c)
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto connected emergency loads through the load sequencer, and operate: for 15 minutes while its generator is loaded with the emergency loads.
- 4.
Verifying the diesel generator operates for at least 60 minutes.
During the first 5 minutes but no greater than 6 minutes of this test I
the diesel generator shall be loaded to greater than or equal to 3248 kw but less than 3300 kw and during the remaining time of this 60 minute test, the diesel generator shall be loaded to greater than or equal to 2750 kw but less than 3000 kw,
- 5.
Verifying that the auto-connected loads to each diesel generator for the worst case diesel generator operating condition do not exceed 3248 kw, and 6.
Verifying that the automatic load sequence timers are OPERABLE with each load sequence time interval within 10%.
This test shall be performed in MODE 3 These revised requirements shall apply only until the end of Cy'le VII.
c The specified 18 month frequency may be waived until the end of Cycle Vll.
CRYSTAL RIVER - UNIT 3 3/4 8 5 Amendment No.123 1
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UNITED STATES t
NUCLEAR REGULATORY COMMISSION WASHINGTON. O. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.123 TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CCRPORATION. ET AL.
CRYSTAL RIVER UNIT NO.- 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 4
lhTRODUCTION By letter dated August 9,1989, Florida Power Corporation (FPC or the licensee) requested an an=ndment to the Technical Specifications (15) appended to Facility Operating License No. OPR-72 for the Crystal River Unit No. 3 Nuclear Generating Plant (CR-3).
The proposed amendment would extend, on a one-time basis, the survelliance interval for the diesel generator full load test until the Cycle Vil reload.
The surveillance interval, as it stands now, ands on.
October 21, 1989, and Cycle Vil reload is scheduled for March 1990.
EVALUATION
-CR-3 has two Emergency Diesel Cenerators (EDG).
The continuous rating of each unit is 2750kW, the 2000-hour rating is 2750kW to 3000kW, and the 30-minute rating is 3000kW to 3300kW. The full load test includes operation for 5 minutes in the 30-minute rating and for 55 minutes in the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating.
Allowable operation in the 30-minute rating, in whicF the maximum engineerec safeguards auto-start load for EDG 1A presently falls, is cumulative.
Currently TS 4.8.1.1.2.d.4 anc 4.8.1.2.2.d.4 require that a full load test be performed every 18 months.
The TS currently allow an extension not to exceed 25%
of the surveillance interval.
Due to an unpinnned outage to repair a reactor coolant pump, the surveillance interval, with maximum extension, runs cut before the end of the current fuel cy cle.
The licensee's proposed changes would allow operation until the end of the current fuel cycle without conoucting the full-load test. This wculd effectively extend the surveillance interval for 5 to 6 months.
The full load tests were last performed on both EDG on December 7,1987.
Since then, EDG 1A has been operated for less than 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, and EDG 1B for less thn 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br />, at an average load of approxicately 2500kW.
EDG 1B has also been operat.o f or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 2900kW.
It is cpected that each EDG will accumulate 60-70 additional hours of operation be%een now and the end of toe current fuel cy cle, in March of 1989, the licensee performed an inspection of both EDG in accordance with the manufacturer's recommendations.
Based on the results of this inspection, it is expected that the EDG will remain capable of supplying the required EV'I &ld"07 N 3 l
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-2 loads until Reload V11.
The run time since the last load test eno the expected additional run time-are small ano the probability of a wear failure in the requetted extension period is low.
In eddition, other EDG tests have been ano will continue to be performed as specified in the TS.
The staff has reviewed the licensee's proposal and, based on the 4,bove, concludes that there is little chance of failure of the EDG to carry the required load in the event of a poss'ulated accident during the requestec extension period.
In
.doitiun, the proposed amendment would increase the time the EDG would be available to carry the maximum engineered safeguards load by eliminating running of the EDG in the 30-minute rating. At the next outage, the system will be modified so that the test loao will be reduced to below the 30-minute rating. We fino, therefore, that the licensee's proposal is acceptable.
EXIGENT CIRCUMSTANCES-In conformanc= with 10 CFR 50.91, the Commission issued a " Notice cf Consideration of Issuance of Amendment to Facility Operating License and Proposite No SignifJ, cant Hazards Consiceration Determination and Opportunity for Hearing" which was published in the Federal Register on September 29, 1989 (54 FR 40221).
As discussed above, the present TS requirements are such that the full load test must be performed by October 21, 1989 or the plant must be shut down.
I' the test were to be conducted, the portion of the test at a power level within the 30-minute rating would reduce the time that the EDG would be available to carry the maxis.um engineered safeguards load.
Therefore, wc conclude that exigent circumstences exist and that the amendment should be issued promptly.
.There were no public coments in response to the Federal Registe.' notice.
FINAL NO SIGNIFICANT HAZAFDS CONSIDERATION DiTERMINATION N Comission's regulations in 10 CFR 50.92 state that the Comission may make final detern.ination that a license amendment involves no significant hazards 3
considerations if operation of the facility in accordance with the amenament would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility cf a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
Operation of the facility in accordance with the proposed amenoment would not involve a significant increase in the probability or consequences of an accident previously evaluated because the ECGS are expected to be capable of performing their intet.ded function for the rem inder of the present fuel cycle.
Operation of the facility in accordance with the proposed amencment would not create the possibility of & aw or cifferent kind of accioent from any accident previously evaluated because the proposed change introduces no new mode of plant operation ncr aces it require any physical modifications to the plant.
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' Operation of the facility in accoroance with the proposed nr.enoment would not involve a significant reduction in a margin of setety because previous tests and inbpections and the low run time since lead us to conclude that the EDGs are expecteo to be capable of carrying thu required load in the event of a postulated accident.
In acdition, not performing the full-load test would increase the nergin of safety since it would increase the length of time the EDG would be available to carry the maximum engineered safeguards load in the event of :.
postulated accident.
i' '
Based on the above, the staf f concludes that the amendment meets the three criteria of 10 CFR 50.92.
Therefore, the staff has made a final determination that the proposed amenoment does not involve significant hazards considerations.
. ENVIRONMENTAL CCHSIDERATION This anends.cnt involves a change in a surveillance requirement.
We have outsrmined that the amenonent involves no significant increase in the amounts, I
and no significant change in the types, of any effluents that may be released i
offsite, and that there is no si occupational radiation exposure.gnificant increase in individual or cumulative i
The Corsnfssion has previously issued a proposed finding that this amendrent involves no significant hazards consideration i
and there has been r:0 public comment on such finding. Accordingly, this amendment freets the eligibility trite.ria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), ra environnental impset statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUS,IM We have concluded, based on the considerations discussed above, that (1) because the requested changes do not involve a significant increase in the probability or consequences of an accident previously evaluated, do not create the possibility of an accident of a type different from any evaluated previously, i
and do nct involve a significarit reduction in a mar in of safety, the amendments co not involve a significant hazards consideration,g(2) there is reasonable osSurance that the health and safety Qf the public Will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Cosmission's regulations and the issuance of this amendrent will not be inimical to the coverun defense ano security or to the health and
'3 safety of the public.
Cated: October 17, 1989 i
principal Contributors:
- 5. Saba C. Wunder j
H. Silver
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