ML20246Q223
| ML20246Q223 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/31/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246Q231 | List: |
| References | |
| NUDOCS 8909110394 | |
| Download: ML20246Q223 (12) | |
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NUCLEAR REGULATORY COMMISSION 5
E WASHING TON. D. C. 20555
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE CITY OF KISSIME CITY OF LEESBURG.
CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES CotEI5510N AND CITY OF ORLANDO SEBRING UTILITIES C0fHI55 ION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAH ASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACIL11Y OPERATING LICENSE Amendment No. Il9 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated December 23, 1988, as supplemented July 12, 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 Commission; 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 amer.dment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of tne Commission's regulations ano all applicable requirements have been satisfied.
8909110394 890831 n'
PDR ADOCK 05000302 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l,
and paragraph 2.C.(2) of facility.perating License No. DPR-72 is hereby l
amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective innediately and shall be implemented within 30 days of issuance.
F0 NUCLEAR REGULATORY C0!EISSION A
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H ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Cate of Issuance:
August 31, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. DPR-72 00 CRIT NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by asendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert VIII VIII XIII XIII 3/4 9-13 3/4 9-14 B3/4 9-3 B3/4 9-3 5-4 5-4 5-5 5-5
l s
i INDEK l
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
SECTION PAGE 3/s.9 PF UELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................
3/4 9-1 l
l 3/4 9 2 INSTRLMEh7ATION..................
3/4 9-2 3/4.9.3 DECAY TIME.....................
3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS..............
3/4 9-4 3/4.9.5 COMMUNICATIONS....................
3/4 9-5 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY..........
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL SIDRA2 POOL BUILDING..
3/4 9-7 3/4.9.8 DECAY HEAT RD40 VAL AND COOLANT CIRCULATION.....
3/4 9-8 All Water Levels..................
3/4 9-8 Low Wa te r Lev el............,......
3/4 9-Ba 3/4.9.9 CONTAINMENT PUR2 AND EXHAUST ISOLATION SYSEM...
3/4 9-9 3/4 9 10 WATER LEVEL - REACTOR VESSEL............
3/4 9-10 3/4.9.11 STORA2 POOL..........,.........
3/4 9-11 3/4 9 12 STORAGE POOL VENTILATION..............
3/4 9-12 3/4.9.13 FUEL ASSEMBLY STORAGE...............
3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4 10-1 3/4.10.2 PHYSICS TESTS...................
3/4 10-2 3/4.10.3 NO FLOW TESTS...................
3/4 10-3 3/4 10.4 SHUTDOWN '4ARGIN..................
3/4 10-4 CRYSTAL RIVER - UNIT 3 VIII Amendment No. III' 119
' ESEd.
If CONDfTIONS FOR OPYRATTI.tMO 3URyggtLaNc3 es SECTION
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I I b 3/s.I1 RAO!OACT.'E EFFLUEivTJ, 5,b$tN Liquid Effluents - Concentration 3/4 11-1 Liquid Effluents - Dose 3/4 11-5 Caseous Effluents - Dose R' ate Dose - Noble Cases 3/5'i17 1
3/4 11-11 i
Dose - I-131, Tritiwn and Radioactive Particulate Total Dose 3/4 11-12 I
3/4 11-14 i
3/4.12-RADICI.OGICAL ENVIRONMENTAL MON!TORING Monitoring Program Land Use Census 3/4 12 I 3/4 12-10 interlaboratory Comparison Program l
3/4 12 '
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CRYSTAL RIVER - UNIT 3 Yma Amendment No. 69, i
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3/4.9.6 FUEL HANDLENG IRIDGE OPERABILTIY......................... B 3/4 9-2 3/4.9.7 GANE 'IRAVEL - SPENT FUEL SICRAGE POOL R.TIIDING.......... B 3/4 9-2 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION................ B 3/4 9-2 3/4.9.9 CI2fIADMENT IUGE AND EXHAUST ISOIATICN SYS'IEN........... B 3/4 9-2 3/4.9.10 NATER I2NEL - REhCIIR VESSEL............................. B 3/4 9-3 3/4.9.11 S'ITRAGE ICOL............................................. B 3/4 9-3 3/4.9.12 S'ITRAGE POOL VENTIIATIN................................ B 3/4 9-3 3/4.9.13 FUEL ASSEMBLY SItRAGE.................................... B 3/4 9-3 3/4.10 SME 'EST & > vuCNS 3/4.10.1 GRX.TP HEIGHI, INSIRIICE AND POWER DISIRIEUTION LIMIIS.............................. B 3/4 10-1 3/4.10.2 RusIcs 'Issrs............................................ B 3/4 10-1 3/4.10.3 No nm TErrS............................................ B 3/4 10-1 3/4.10.4 SICIID W MMGIN.......................................... B 3/4 10-1 l
1 l'
A'nendment No. H.II7, II9 CRESTAL RIVIR - (NIT 3 XIII L_
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E aAsEs 5 !r0" 558tE 3/4.11 RAD 10ACTrvE EFm.im;wt 3/4.11.1.1 LQUID EFFLUENTS - CONCENTRATION i
& 3/4 11 1
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3/4.11.1.2 LIQUID EFFLUENTS - DOSE B 3/4 11 1 3/4.11.2.1 GASEOUS EFFLUENTS - DOSE RATE B 3/4 11-2 3/4.11.2.2 GASEOUS EFFLUENTS - DOSE, NOBLE GASE5 B 3/4 11 2 3/4.11.2.3 GASEOUS EFFLUENT 5 - DOSE,3131, TRIT!UM AND RADIOACTIVE PARTICULATE B 3/4 11 3-3/4.11.3 TOTAL DOSE B 3/4 11 4 3/4.12 R RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12 1 3/4.12.2 LAND USE CENSUS B 3/4 12 1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12 1 1
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i CRYSTAL RIVER - UNIT 3 XIlla Amen hent No. 69 I
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3/4,9.13 M.M 51GER r1-ym u
_.,. _.. -..m 3.9.13 naal assemblies shall be stored in locations in moocedance with coniiticms as specified below:
IDCATICH GMDITIM
- 1. - Dry fLael storage racks How fuel with initial enrictment S.4.5 wai@t percent U-235 2.
Storage Pool A Maal with initial enrictment and burnup in acocedance with Figure 3.9-1 but S 4.5 wai@t y
e U-235 3.
Storage Pool B Maal with initial enriciment S 4.0 wai@t y - i U-235 APPLICABILITY: ihenever fuel assemblies are in the fuel h r,. locations.
KIEt!:
a.
With the recpirements of the abcwe if4= tion not satisfied, suspend all other acwoment of fuel ammeublias and crane operaticns with loads in the foal storage areas and nrwe the rzi m lying fuel assemblies to their penpar designated locations.
In addition, with the regairements of the abcue sps::ification for storage pools A or B not antisfied, boren cxmountration of the spent fuel pools shall be verified to be greater than or equal to 1925 pput at least anoe par 8 hcurs.
b.
The pcevisions of Specifications 3.0.3 and 3.0.4 are not applicable.
w 11 M N T In r y rI NED E N T S 4.9.13.1 Verify the initial enrichment of new f.nal assemblies 5 4.5 weight percent U-235 pr2.ct to sh.g. in the dry fuel stcrage racks.
4.9.13.2 Performt an INDEFENII2C VERIFIO1ICH of the initial enrictuant and burrup of fuel asaanblies in armniance with Figure 3.9-1, prior to storage in the pool A storage racks.
A ots@lete recxad of such analysis shall be kept for the time period that the fuel annambly remains in the pool A mL.u..ip. racks.
4.9.13.3 Verify the initial enrictanent of fuel assemblies S 4.0 weight mi U-235 prior to shu..q. in pool B storage racks.
Amendment No.119 CRYSRL RIVER - (2CET 3 3/4 9-13
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Figure 3.9-1
' Minimum Required Fuel Assembly Burnup os a Function
'of initial Enrichment to Permit Storoge in Pool A
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8.0 (4.5.7.0) i 6.0 E
s ACCEPTABLE FOR R
POOL A STORAGE 2
5.0 4.0 U
Iw 3.0 d
E 2.0 i
i NOT ACCEPTABLE 1.0 FOR POOL A STOPAGE I
( 3.5,0.0) 0.0 O.O O.5 1.0 1.5 2.0 E.5 3.0 3.5 40 4.5 5.0 5.5 FUEL ASSEMBLY INIT!AL ENRICHMENT, W/O U-235 1
CRYSTAL RIVER - UNIT 3 3/4 9-14 Amendment No.119 L_
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REFUELING OPERATIONS BASES l
l 3/4.9.10 WATER LEVEL - REACTOR VESSEL WATER LEVEL The restrictions on minimum water. level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4.9.11 STORAGE POOL The requirement formissile shields'io be installed over the storage pool ensures that the tornado missile protection assumptions are satisfied.
The restrictions on minimum water level ensure the sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4.9.12 STORAGE POOL VENTILATION The requirement for the auxiliary building ventilation exhaust system srJvicing the storage pool are to be OPERABLE ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal absorber prior to discharge to the l
atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
3/4.9.13 FUEL ASSEMBLY STORAGE The restrictions placed on fuel assembly storage ensure inadvertent criticality will not occur.
I CRYSTAL RIVER - UNIT 3 B 3/4 9-3 Amendment No. 777,119
l M FWNE MEnaf MIEEEEE AIE)1BetimEIE 5.2.2 The Remetor Ctritairmant. N4 Ming is designed and shall be maintained for a maximum internal pressure of 55 psig and a tamparature of 281*F.
5.3 N 1 CIEEE FML AEBEE2ES 5.3.1
'!he reactor core shall contain '177 fuel namenMies with each fuel assembly containirq 208 fuel rods clad with Zircalcy - 4.
Each fuel rtxi shall have a rzminal active fuel langth of 144 inches and corf.ain a nav4== total waicAt of 2253 grams uranium.
The initial care loading shall have a nav4== anridment of 2.83 =iM WA. U-235.
Aaloed fuel shall be similar in physical design to the initial core loadirq armi shall have an enridument less than or equal to 4.2 nominal weight parcent U-235.
i cramc0 IEms 5.3.2
'The reactor core shall contain 60 safety and regulating (including extended life control rods) and 8 axial power shaping (APSR) control rods. Except for the extended life control rods, the safety and regulating control rods shall contain a nominal 134 inches of absorber material. The extended life control rods shall contain a nominal 139 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium, and 5 percent cadmium.
Except for the extended life control rods, all control rods shall be clad with stainless steel tubing. The extended life control rods shall be clad with Inconel. The APSRs shall contain a nominal 63 inches of absorber material at their lower ends. The absorber material for the APSRs shall be 100% Inconel.
1 CRHfIAL RIVI:R - UNIT 3 5-4 Amendment No. 16.35,72.77,H.193, 119
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4 M FEEGE 5,4 m GIIAllt sMEnt M m AE 1BEWIunME:
3 5.4.1
'me reactor tvm'larit system is designed and shall be unintained.
In acreedance with the code regairements specified in Section
{
a.
4.1.2 of the FSAR, with allcumnae f<r normal degradaticri pursuant to applicable Surveillance Requirements, b.
Ptr a pressure of 2500 psig, and c.
Ptr a temperature of 650'F, exempt for the pressurizer ard pressurizer surge line, Wiicti.is 670*F.
EIDE 5.4.2
'me total water ard stamm voltane of the reactcr coolant systee is 12,180 3 200 cubic feet at a nominal T of 525'F.
avg 5.5 nerunnrry rCAL TNest T_M_CN 5.5.1
'!he meteorological tower shall be located as shown cm Figure 5.1-1.
i 5.6 p wr,gratg g QUTIGLLT1Y 5.6.1
'ma dry fuel storage racks and spent fuel storage racks are designed and shall be maintainst with:
a.
A Magg less than or equal to 0.95 Wan flooded with unborated water, W11ch ircludes a conmarvative allowance for uncertainties.
This 15 based on new fuel with a maximum initial enrichment of
~
4.5 weight percent U-235 in dry fuel storage racks, on fuel with combinations of initial enrichment and discharge burnup as shown in Figure 3.9-1 in storage pool A, and on fuel with a maximum initial enrichment of 4.0 weight percent in storage pool B; b.
A trainal 10.5 incts omntar-t&<mntar distance between fLul mamard,1ies placed in the high density h+ racks in pool A; and c.
A noudnal 21.125 irch contar-to-contar distance between fuel assemblies plaond in the dry fuel storage racks and storage j
racks in pool B.
13tkIMME 5.6.2
'me sp fuel h+ pool is designed ard shall be maintained to prwvent inadvertent draining of the pool belcw elevation 138 feet 4 inctes.
l mYS'DLL RIVER - INIT 3 5-5 Amendment !!o. 36,72,72, 119
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