ML17221A676
| ML17221A676 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/11/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17221A675 | List: |
| References | |
| NUDOCS 8803210477 | |
| Download: ML17221A676 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLAPIDA POWER E
LIGHT COMPANY DACKET NO. 50-335 ST.
LUCIE PLANT UNIT N0. I AHFNDMENT TO FACILITY OPFPDTING LICENSF Amendment No.
91 License No.
DPR-67 1.
The Nuclear Pegulatory COIImission (the Commission) has found that:
A.
The apnlication for amendment by Florida Power 8 Light Company, (the licensee) dated June 12, I.G87, as supplemented by ~etters dated September 8, 1987, October 20, 1987 (three letters),
December 21,
- 1987, December 22,
- 1987, December 23, 1987 (three letters),
and January 29, 1988, complies with the standards and reouirements 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 con<ormity with the application, the provis'ons of the Act, and the rules and requlations 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 Comnission's regulations; D.
The issuance of this amendmen, wi.ll not be inimical to the common defense and security or to the health and safety of'he public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comissinn's regulations and all applicable requirements have been satisfied.
8803220477 8803ll PDR ADQCK 05000335 P
2.
Accordingly, Facility Operating License No.
DPR-67 is amended by changes tn the Technical Speci+ications as indicated in the at+achment
+o this 1'cense amendment, and by amending paragraph 2.C.(2) to read as follows..
(2)
Technical S ecifications The Technical Specifications contained in Appendices A
and 8, as revisid throuah Amendment No.
91
, are hereby incoroorated in the license.
The licensee shall operate the fac.'lity in accordance with the Technical Specifications.
3.
This license amendment is effective as o+ the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.erbart N. Berkow, Director Pro ect Directorate II-2 Division of Reactor Prospects-I/II Office of Nuclear Reactor Regulatinn
Attachment:
Charges to the Technical Specifications Date of Issuance:
March 11, 1988
ATTACHMENT TO LICENSE AMFNDMENT NO, 91 TO FACILITY OPERATING LICFNSF.
NO.
DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed paqes.
The revised pages are identified by amendment number and contain vertical l-:nes indicating the area of change.
The corresponding overleaf pages are also provided to maintain document com-pleteness.
Remove Paces B 3/4 9-3 5-6 Insert Pa es B 3/4 9-3 5
5-6 5-6a 5-6b
REFUELING OPERATIONS BASES 3/4.9.12 FUEL POOL VENTILATION SYSTEM-FUEL STORAGE The limitations on the fuel handling building ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assump-tions of the accident analyses.
3/4.9.13 SPENT FUEL CASK CRANE The maximum load which may be handled by the spent fuel cask crane is limited to a loaded single element cask which is equivalent to approxi-mately 25 tons.
This restriction is provided to ensure the structural integrity of the spent fuel pool in the event of a dropped cask accident.
Structural damage caused by dropping a load in exceed of a loaded single element cask could cause leakage from the spent fuel pool in excess.of the maximum makeup capability.
3/4.9.14 DECAY TIME -
STORAGE POOL The minimum requirements for decay of the irradiated fuel assemblies in the entire spent fuel storage pool prior to movement of the spent fuel cask into the fuel cask compartment insure that sufficient time has elapsed to allow radioactive decay of the fission products.
The decay time of 1180 hours0.0137 days <br />0.328 hours <br />0.00195 weeks <br />4.4899e-4 months <br /> is based upon one-third of a core placed in the spent fuel pool each year during refueling until the pool is filled.
The decay time of 1490 hours0.0172 days <br />0.414 hours <br />0.00246 weeks <br />5.66945e-4 months <br /> is based upon one-third of a core being placed in the spent fuel pool each year during refueling following which an entire core is placed in the pool to fill it.
The cask drop analysis assumes that all of the irradiated fuel in the filled pool (7 2/3 cores) is ruptured and follows Regulatory Guide 1.25 methodology, except that a Radial Peaking Factor of 1.0 is applied to all irradiated assemblies.
ST.
LUGIE - UNIT 1
B 3/4 9-3 Amendment No. gf.
gH~
DESIGN FEATURES CONTROL ELEMENT ASS EMBLI ES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.
The control element assemblies shall be designed and maintained in accordance with the original design provisions contained in Section
- 4. 2.3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
- 5. 4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
C.
For a pressure of 2485 psig, and For a temperature of 650'F, except for the pressurizer which is 700'F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,100
+ 180 cubic feet at a nominal T
of 567'F.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
- 5. 6 FUEL STORAGE CRITICALITY 5.6.l.a The spent fuel storage racks are designed and shall be maintained with:
l.
A k ff equivalent to less than or equal to 0.95 when flooded witk unborated water, which includes a conservative allowance of 0.0065 ak for uncertainties.
ST.
LUGI E - UNIT 1
5-5 Amendment No. gg,g7, 7$,
91
DESIGN FEATURES CRITICALITY (Conti nued 2.
A nominal 10.12 inches center to center distance between fuel assemblies in Region 1 of the storage racks and a nominal 8.86 inches center to center distance between fuel assemblies in Region 2 of the storage racks.
3.
A boron concentration greater than or equal to 1720 ppm.
4.
Neutron absorber (boraflex) installed between spent fuel assemblies in the storage racks in Region 1 and Region 2.
b.
Region 1 of the spent fuel storage racks can be used to store fuel which has a 'U-235 enrichment less than or equal to 4.5 weight per cent.
Region 2
can be used to store fuel which has achieved sufficient burnup such that storage in Region 1 is not required.
The initial enrichment vs.
burnup requirements of Figure 5.6-1 shall be met prior to storage of fuel assemblies in Region 2.
Freshly discharged fuel assemblies may be moved temporarily into Region 2 for purposes of fuel assembly inspection and/or repair, provided that the configuration, is maintained in a checkerboard pattern (i.e., fuel assemblies and empty locations aligned diagonally).
Following such inspection/repair activities, all such fuel assemblies shall be removed from Region 2 and the requirements of Figure 5.6-1 shall be met for fuel storage.
c.
The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal, to 4.0 weight percent, while maintaining a
k ff of less than or equal to 0.98 under the most reactive condition.
DRAINAGE 5.6.2 The fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.
CAPACITY 5.6.3 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1706 fuel assemblies.
- 5. 7 SE ISHI C CLASSIFICATION 5.7.1 Those structures, systems and components identified as seismic Class I
in Section 3.2.1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3.7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirement.
ST.
LUGIE - UNIT 1
5-6 Amendment No. J7,R2,2R~HR.
7$ i 91
DESIGN FEATURES 5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower location shall be as shown on Fi'gure 5.1-1.
5.9 CO!1PONENT CYCLE OR TRANSIENT LIMITS 5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1.
ST.
LUGIE - UNIT 1
5-6a Amendment No.
91
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April 297 1988 TRIBUTION 0 cket File w/o encl,:
PD22--Reading w(o encl.
D. i~1iller w/encl, E. Tourigny w/encl, DOCKET NO(S).
50 335 and 50 389 Nr. W. F.
Conway Acting Group Vice President Nuclear Energy FLorida Power and Light Company P.O.
Box 14000 Jenny Beach, Florida 33408 The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.
dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideratipn of Issuance of Facility Operating License or Amendment to Facility Operating License, dated gg Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No Significant Hazards Considerations, dated 4/20/88
[see page(s) j Exemption, dated Construction Permit No.
CPPR-
, Amendment No.
dated
+ Facility Operating License No.,
Amendment No.
dated Order Extending Construction Completion Date, dated t)onthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Encl osures:
As stated Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation cc: See next page OFFICE SURNAMK)
PATE1 3t 2 e ~ ~ ~ ~ ~
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iM'"'RC FORM 318 RO/801 HRCM 0240 OFFIC)AL RECORD COPY
April 21, 1988 DISTRIBUTION
.Mk
-F!1.
PD22 Reading w(o encl, D, Hi,lier w(encl, E, Tourigny w('encl, DOCKET NO(S).
50-335 and 50 389 ti. H. F. Conway Acting Group Vice President Nuclear Energy FLorida Power and Light Company P.O.
Box 14000 Juno Beach, Florida 33408
SUBJECT:
ST.
LUCIE PLANT UNITS 1
AND 2 The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.
dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License, dated X Hi-Meekly Notice; Applications and Amendments to Operating Licenses Involving No if' d
C id i
d d~4l (i]
Exemption, dated Con'struction Permit No.
CPPR-
, Amendment No.
dated Facility Operating License No.
, Amendment No.
dated Orcler Exte'nding Construction Completion
- Date, dated
+ tdonthly (peratlng Report for transmitted by letter dated
+ Annual/Semi-Annual Report-transmitted by letter dated Encl osures:
As stated Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation cc:
See next page DFFice~
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NRC FORM 318 llOIBOINRCM 0240 OFFICIAL RECORD COPY