ML20207E794
| ML20207E794 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/21/1999 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20137S422 | List: |
| References | |
| NUDOCS 9906070153 | |
| Download: ML20207E794 (18) | |
Text
r-LAR 98-0007 Page 25 INDEX 4
IlMITING CONDITIONS FOR OPERATION AND SURVEHI ANCE REQUIREMENTS SECTION
~
PAGE 3/4.9 REFUELING OPERATIONS l
.3/4.9.1 B ORON CONCENTRATION.........................................
3/49-1 3/4.9.2 INSTRUMENTATION...............................................
3/49-2 l
3/4.9.3 DEC A Y TIM E......................................................
3/49-3 3/4.9.4 CONTAINMENT PENETRATIONS....................................
3/49-4 3/4.9.5 D ELETED........................................................
3/49-5 3/4.9.6-FUEL HANDLING BRIDGE OPERABILITY............................
3/49-6 3/4.9.7 CRANE TP'AVEL - FUEL HANDLING BUILDING.......................
3/49-7 3/4.9.8 - DECAY HEAT REMOVAL AND COOL'ST CIRCULATION l
All Water Levels................................................
3/49-8 low Water Levels...............................................
3/4 9-8a l
3/4.9.9 DELETED........................................................
3/49-9 1
3/4.9.10 WATER IEVEL - REACTOR VESSEL................................
3/4 9-10 3/4.9.11 - STORAGE POOL WATER LEVEL....................................
3/4 9-11 3/4.9.12 STORAGE POOL VENTILATION.............................. -.......
3/4 9-12 l
3/4.9.13 SPENT FUEL POOL "JEL ASSEMBLY STORAGE......................
3/4 9-13 i
3/4.10 SPECIALTEST EXCEPTIONS l
3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..........................................................
3/4 10-1 l
3/4.10.2 PHYSICS TESTS...................................................
3/4 10-2 3/4.10.3 REACTOR COOLANT LOOPS........................................
3/4 10-3 3/4.10.4 S HUTDOWN MARGIN..............................................
3/4 10-4 1
DAVIS-BESSE, UNIT 1 VIII Amendment No. 38,130,186,
- 224, 9906070153 990521 U
PDR ADOCK 05000346 P
-s.
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LAR 98-0007 Pag 326 INDEX BASES SECTIQM 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY........................... B 3/4 9-2 1
1
-3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING..................... B 3/4 9-2 l
l 3/4.9.8 COOLANT CIRCULATION......................................... B 3/4 9-2 l
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3/4.9.9 DELETED...................................................... B 3/4 9-2 1
i 3/4.9.10 and 3/4.9.11 WATER LEVEL - REAC'IDR VESSEL AND S'IURAGE POOL............................................. B 3/4 9-2 3/4.9.12 STORAGE POOL VENTILATION..................................... B 3/4 9-3 l
3/4.9.13 SPENT FUEL POOL "JEL ASSEMBLY STORAGE...................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.....
B 3/410-1 3/4.10.2 PHYSICS TESTS................................................... B 3/410-1
' 3/4.10.3 REACTOR COOLANT LOOPS.......................................
B 3/410-1 3/4.10.4 SHUTDOWN MARGIN.............................................
B 3/410-1 l
l 3/4.11 RADIOACTIVE EFFLUENTS l
l 3/4.11.1 LIQUID HOLDUP TANKS........................................... B 3/411-1 l
3/4.11.2 EXPLOSIVE GAS MIXTURE........................................
B 3/411-1 1
3/4.12 DELETED l
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- DAVIS-BESSE, UNIT 1 XIII Amendment No. 86,130,135,170,186, 1
1
n LAR 98-0007 Page 27-L INDEX i
l DESIGN FEATURES SECTION PAGE.
5.1 Site Location 5-1 ilDeleted 5.3 Reactor Core Fuel Assemblies.........................................
5-1 l
Control Rods............................................
5-1 14 Deleted ilDeleted 5.6 Fuel Storane
~ Cri ticality..............................................
5-1 Drai n a ge..............................................
541 Cap aci t y...............................................
542 1,2 Deleted DAVIS-BESSE, UNIT 1 XIV Amendment No. 38,170,204,
r;:
LAR 98-0007 Page 28 -
REFUELING OPERATIONS CRANE TRAVEL - FUEL HANDLING BUTIDING
' LIMITING CONDITION FOR OPERATION
. 3.9.7 Loads in excess of 2430 pounds shall be prohibited from travel over fuel assemblies
'in the spent fuel pool or in the cask oit.
APPLICABILITY: With fuel assemblies and water in the spent fuel pool or in the cask sil.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
/
. SURVEILLANCE REQUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly, shall be verified to be s 2430
- po prior to moving it over fuel assemblies in the spent fuel pool or cask oit.
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- DAVIS-BESSE, UNIT 1 3/49-7 Amendment No.
i LAR 98-0007 Page 29 REPUELING OPERATIONS STORAGE POOL WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 As a minimum,23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks in the snent fuel nool or cask nit.
APPLICABILITY: Whenever irradiated fuel assemblies are in the soent fuel nool or enk d0ter".5 pccl.
ACI' ION:
With the requirement of the specification not satisfied, suspend all movement of fuel and crane operations with loads in the fuel storage area and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the soent fuel nool and cask oit stcr ;; pec! shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in these locations $ fuel :terage pec!.
DAVIS-BESSE, UNIT 1 3/4 9-11 Amendment No.
p
r LAR 98-0007 Page 30 REFUELING OPERATIONS STORAGE POOL VENTILATION LIMITING CONDITION FOR OPERATION 3.9.12 Two independent emergency ventilation systems servicing the storage pool area shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the spent fuel nool or cask oit d:.;;:
=d.
ACTION:
- a. With one emergency ventilation system servicing the storage pool area inoperable,.
fuel movement within the scent fuel cool or cask oit. ca.;;; p::! ar crane operation with loads over the soent fuel oool or cask oit. der.;;: pre! may proceed provided the OPERABLE emergency ventilation system servicing the storage pool area is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.
- b. With no emergency ventilation system servicing the storage pool area OPERABLE, suspend all operations involving movement of fuel within the spent fuel cool or cask g d:.;;; p::! or crane operation with loads over the soent fuel oool or cask oit.
skwage peel-until at least one system is restored to OPERABLE status.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
-i 4.9.12.1 The above required emergency ventilation system servicing the storage pool area shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.6.5.1,'and at least once each REFUELING INTERVAL by verifying that the emergency ventilation system servicing the storage pool area mainta*ms the storage pool area at a negative pressure of 21/8 inches Water Gauge relative to the outside atmosphere during system operation.
4.9.12.2 The normal storage pool ventilation system shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by verifying that the system fans stop automatically and that dampers automatically divert flow into the emergency ventilation L system on a fuel storage area high radiation test signal.
DAVIS-BESSE, UNIT 1 3/4 9-12 Amendment No. 135,217,
LAR 98-0007 Page 31 7
REFUELINO OPERATIONS SPENT FUEL POOb-FUEL-ASSEMBLY STORAOE LIMITINO CONDITION FOR OPERATION 1.9.13 Fuel assemblies shall be olaced in the spent fuel storane racks in accordance with tm fo owino criteria:
3A44 g Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel storage racks in accordance with the criteria shown in Figure 3.9-1.
- b. Fu:1 assemblies stored in he emek oit shall be n1amd in the soent fuel storane raccs in accordance witi tx criteria shown in Fleure 3.9-2.
APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool or cask oit.
A. TION:
C l
With the requirements of the above gpecifications 3.9.13.a or 3.9.13.b not satisfied, suspend all other fuel movement within the spent fuel pool or case oit and move the non-complying fuel assemblies to allowable locations ir. $: ;;n: fr p :! in accordance with Figure 3.9-1 for the soent fuel nool. or Finure 3.9-2 for the==k oit. as espiooriate.
'Ihe provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13.1 Prior to storing phe fuel assembly in the spent fuel pool or cask oit. verify by administrative means that the initial enrichment and burnup of the fuel assembly are in accordance with Figure 3.9-1 for the soent fuel cool. or Finure 3.9-2 for the cask oit. as anp a ints 1
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DAVIS-BESSE, UNIT 1 3/4 9-13 Amendment No. 130,181, l.
i
LAR 98-0007 Page 32 Figure 3.9-1 Burnup vs. Enrichment Curves For Davis-Besse Spent Fuel Ep.glStorage Racks 60 50 "A"
- 5.0.44.2 s g
40 d
(4.5,37.8 [
t
'Q (4.0,32.6) 30 (3.5,28.4 [
Allowed
- s M
(3.0,23.
Eo 20
[
(2.5,17.9 "B"
(5.0,10.g (4.5, 7.9 (4.0,4.4) 0 l.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 Initial Enrichment (wt% U-235)
Category "A": May be placed in any rack location Category "B": Must not be placed directly adjacent to Category "C" assemblies Category "C": May only be placed directly adjacent to Category "A" assemblies or non-fuel locations DAVIS-BESSE, UNIT 1 3/4 9-14 Amendment No. 130,181,
LAR 98-0007 Page 33 Figure 3.9-2 Burnup vs. Enrichment Curve for Davis-Besse Cask Pit Storage Racks 60 I
(5.05, 53.51 50 -
ACCEPTABLE DOMAIN (4.50,43.29) 40
/
n NOT s
g (4.00,34.51) n.
30 -
.a:-
(3.50,25.17-G
$4 20 -
(3.00,18.80)
(2.50,12.43)
UNACCEPTABLE DOMIN 10 d
(2.00,4.92) 0 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 initial Enrichment (wt% U-235)
Note: Fuel assembies with initial enrichments less than 2.0 wt% U 235 will conservatively be required to meet the burnup requirements of 2.0 wt% U-235 cssemblies.
DAVIS-BESSE, UNIT 1 3/4 9-15 Amendment No.
LAR 98-0007 Revised byNRCletterdated:
Pag) 34 August 12.1994 REFUELING OPERATIOlg BASES 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY
'Ihe OPERABILITY requirements of the hoist bridges used for movement of fuel assemblies ensures that: 1) fuel handling bridges will be used for movement of control rods and fuel assemblies,2) each hoist has sufficient load capacity to lift a fuel element, and 3) the core intemals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during liftmg operations.
3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING 1 The restriction on movement ofloads in excess of the nominal weight of a fuel assembly in n.
failed fuel container over other fuel assemblies in the spent fuel nool o can c nit e6esege peel ensures that in the event this load is dropped (1) the acuvny release wi i r o exceed he source erm essumed in the desian ude fael hann no accidant for out im conta i
r nen = ;==: =
= ::-----
- r. : :-
- =: rrcc:-, am g) any,possione aimruon on act m the storage racks will not result in a critical array.h.i: r: -;:::: i: =r9--! --ii i: - " tity r!:rr r m d ir. 1: rid et-- 'y:=.
3/4.9.8 COOLANT CIRCULATION The requirement that at least one decay heat removal loop be in operation ensures that (
1 sufficient coolm' g capacity is available to remove decay heat and maintain the water in t pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.
The req uirement to have two DHR loo >s OPERABLE when there is less than 23 feet of water l
above tlie core ensures that a single faEure of the operating DHR loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sirik is available for core cooling. Thus, in the event of a
- failure of the operating DHR loop, adequate time is provided to initiate emergency procedures to cool the core.
l In MODE 6, the RCS boron concentration is typically somewhat higher than the boron concentration required by Specification 3.9.1, and could be higher t um the boron concentration of normal sources of water addition. The flowrate through the decay heat system may at times be reduced to somewhat less than 2800 gpm. In this situation, if water with a boron concentration equal to or greater than the boron concentration required by Specification 3.9.1 is added to the RCS, the RCS is assured to remain above the Specification 3.9.1 requirement, and a flowrate of less than 2800 gpm is not ofconcern.
3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM Deleted 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL
'Ihe 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. 'Ihe minimum water depth is consistent with the assumptions of the safety analysis.
DAVIS-BESSE, UNIT 1 B 3/4 9-2 Amendment No. 38,135,186
- 188,
~
LAR 98 0007-Page 35,
REFUELING OPERATIONS BASES-3/4.9.12 STORAGE POOL VENTILATION The requirements on the emergency ventilation system servicing the storage pool.
area to be operating or OPERABLE ensure 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 assumptions of the safety analyses.
3/_4.9.13 SPENT FUEL P^^L FLTL ASSEMBLY STORAGE The restrictions on the placement of fuel assemblies within the spent fuel pool _and cask oit. as dictated by Figure 3.9-1 and Figure 3.9-2, ensure that the k-effective of the spent fuel pool and cask oit will always remain less than 0.95 assuming the spent fuel cool and cask pit eeel-to be flooded with non-borated water. The restrictions delineated in Figure 3.9-1 and Finure 3.9-2. and the action statement, are consistent with the criticality safety analysps performed for the spent fuel pool and cask pit.
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DAVIS-BESSE, L NIT.1 -
B 3/4 9-3 Amendment No. 130,135, IJ
LAR 98-0007:
Design Features Page 36 5.0
- 5.0 DESIGN FENIURES 5.1 Site Imation De Davis-Besse Nuclear Power Station, Unit Number 1, site is located on Lake Eric in Ottawa County, Ohio, approximately six miles northeast fmm Oak Harbor, Ohio and 21 miles east from Toledo, Ohio.
He exclusion area boundary has a minimum radius of 2400 feet from the center of the plant.
5.2 (Deleted) 53 Reactor Core ~
ADDl!!0NAL CHANGES PREVIOUSLY-PROPOSED BY LETTER 53.1 Fuel Assembh.es.
ScialNo. Z 5 5L Date T[8/98 The reactor core shall contain 177 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited substitutions of zirconium alloy 2
or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC stasapproved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number oflead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
53.2 Control Rods De reactor core shall contain 53 safety and regulating controt rod assemblies and 8 axial power shaping rod (APSR) assemblies. He nominal values of absorber material for the safety and regulating controt rods shall be 80 percent silver,15 percent indium and 5 percent -
cadmium. He absorber material for the APSRs shall be 100 percent Inconel.
5.4 (Deleted) 1 5.5 (Deleted) 5.6 Fuel Storage 5.6.1 Criticality -
5.6.1.1 He spent fuel gggi storage racks are designed and shall be maintained with:
a.
A Kegequivalent to less than or equal to 0.95 when flooded with unborated water,
~ which includes a conservative allowance of 1% delta k/k for calculation uncertainty, i
(continued) 1 DAVIS BESSE, UNIT I -
5-1 Amendment No. 170,179,204,
F 1
LAR 98-0007 Page 37 Design Features 5.0 5.0 DESIGN FEATURES 5.6 Fuel Storage (continued)
- b. A rectangular array of stainless steel cells spaced 12 31/32 inches on centers in one direction and 13 3/16 inches on centers in the other direction. Fuel l
assemblies stored in the spent fuel pool shall be placed in a stainless steel cell of 0.125 inches nominal thickness or in a failed fuel container.
Fuel assemblies stored in the spent fuel pool in accordance with Technical c.
Specification 3.9.13.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
l A K,, equivalent to less than or equal to 0.95 when flooded with unborated a.
water, which includes a conservative allowance of 1% delta k/k for uncertainties as described in Section 9.1 of the USAR.
- b. A K,, equivalent to less than or equal to 0.98 when immersed in a hydrogenous
" mist" of such a density that provides optimum moderation (i.e., highest value of K,,), which includes a conservative allowance of 1% delta PJk for uncertainties as described in Section 9.1 of the USAR.
- c. A nominal 21 inch center-to-center distance between fuel assemblies placed in the storage racks.
- d. Fuel assemblies having a maximum initial enrichment of 5.0 weight percent uranium-235.
5.6.1.3 ne cask oit storace racks are desicned and shall be maintained with:
I a.
A K,y couivalent to less than or eaual to 0.95 when flooded with unborated water. which includes a conservative allowance for manufacturine tolerances and calculation uncertainty.
- b. A rectancular array of stainless steel cells spaced a nominal 9.22 inches on center in both directions. Boral neutron absorber material is utilized between each cell for criticality considerations. Fuel assemblies stored in the cask nit shall be placed in a stainless steel cell with walls of 0.075 inches nominal thickness.
c.
Fuel assemblies stored in the cask nit in accordance with Technical Specification 3.9.13.
DAVIS-BESSE, UNIT 1 5-2 Amendment No. 204,
1 LAR 98-0007 i
Paga38 Design Features ifl DESIGN FEATURES 5.6 Fuel Storace (continued) 1 5.6.2 Drainace l
The spent fuel storage pool and cask oit are iexiesigned and shall be maintained to l
prevent inadvertent draining of the pee! Selow 9 feet above the top of the fuel storage racks.
5.6.3 Canacity gThe spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 735 fuel assemblies.
- b. The cask nit is desinned and shall be maintained with a storace canacity limited to no more than 289 fuel assemblies.
5.7 (Deleted) 1 DAVIS-BESSE, UNIT 1 5-}
Amendment No. 204,
F Docket Number 50-346.
License Number NPF-3 Serial Number 2550 Page1 ENVIRONMENTAL ASSESSMENT FOR LICENSE AMENDMENT REQUEST NUMBER 98-0007 Identification of Prooosed Action This proposed action involves the Davis-Besse Nuclear Power Station (DBNPS), Unit 1.
Operating License Number NPF-3, Appendix A, Technical Specifications (TS). The
. proposed license amendment application involves TS 3/4.9.7, Refueling Operations - Crane Travel - Fuel Handling Building, and associated Bases; TS 3/4.9.11, Refueling Operations -
Storage Pool Water Level; TS 3/4.9.12, Refueling Operations - Storage Pool Ventilation; TS 3/4.9.13, Refueling Operations - Spent Fuel Pool Fuel Assembly Storage, and associated Bases; TS 5.6, Design Features - Fuel Storage; and related changes to the TS Index.
. The proposed TS changes would expand the present spent fuel storage capability by up to 289 storage locations by allowing the use of spent fuel racks in the cask pit area adjacent to the spent fuel pool (SFP). The cask pit is accessible from the SFP through a gated opening in
' the wall dividing the two pool areas.
Need for the Proposed Actip.n A facility for the long-term storage of spent nuclear fuel assemblies from commercial nuclear power reactors is to be provided by the United States Department of Energy. However, since such a facility is not yet available or expected to be available until at least the year 2010, commercial nuclear power plants, such as the DBNPS, have had to provide for additional spent fuel storage.
The DBNPS began the current operating Cycle 12 with insufficient storage capacity in the SFP to fully offload the entire reactor core (177 fuel assemblies). The current spent fuel storage capacity in the spent fuel pool is 735 fuel assemblies. There are currently only 114 empty storage locations available in the spent fuel pool. A full core offload into the spent fuel pool is required for the performance of the ten-year Inservice Inspection activities required during the Twelfm Refueling Outage (12RFO), which is scheduled to commence in April 2000.
' Following the core reload during 12RFO, with 72 fuel assemblies scheduled to be permanently discharged, there would be only 42 empty storage locations available in the spent fuel pool. Refueling of the reactor during the Thirteenth Refueling Outage (13RFO),
j which is scheduled to commence in Spring 2002, would not be possible since there would be i
insufficient empty storage locations available to hold the 72 fuel assemblies scheduled to be permanently discharged.
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Docket Number 50-346 H
- License Number NPF-3 Serial Number 2550 '
L Attachment 2 -
Page 2 Environmental Imnact of the Pronosed Action-As described in the Safety Assessment and Significant Hazards Consideration (SASHC) for the proposed license amendment application, the DBNPS has determined that the structures, systems, and components which could be affected by the proposed license amendment, will continue to be capable of performing their safety functions.
The proposed license amendment application involves a change to a requirement with respect to the use of plant components located within the restricted area as defined in 10 CFR Part 20. As discussed in the SASHC, this proposed license amendment does not i
' involve a significant hazards consideration. The proposed change to allow the use' of spent fuel racks installed in the cask pit area does not alter source terms, containment isolation, or allowable releases. In addition, as described in further detail below, the proposed change does not involve an increase in the amounts, and no change in the types, of any radiological effluents that may be allowed to be released offsite. Furthermore, as also described in further detail below, there is no increase in the individual or cumulative occupational radiation exposure.
The spent fuel pool cooling and cleanup system currently generates approximately.
50 cubic feet of solid radioactive waste annually. The necessity for pool filtration resin replacement is determined primarily by the need for water clarity, and the resin is normally changed about once every 18 months. The additional number of fuel assemblies in storage is not expected to significantly affect the resin replacement
' frequency. Therefore, no significant increase in the volume of solid radioactive waste is expected from operating with expanded spent fuel storage capacity.
The number of stored spent fuel assemblies does not affect the release of radioactive liquids from the plant. The contribution from the stored fuel assemblies of radioactive materials in the spent fuel pool water is insignificant relative to other sources of activity, such as the reactor coolant system. The volume of spent fuel pool water processed for' discharge is independent of the quantity of stored spent fuel assemblies.
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- The contribution of gaseous releases from the fuel storage area is negligible in I
comparison to other releases, and no significant increase due to the increased quantity of stored spent fuel assemblies is expected. The discharge of gaseous radioactive -
l effluents will continue to be a small fraction of regulatory limits.
j.
During normal operations, personnel working in the fuel storage area are exposed to l
radiation from the spent fuel pool. Operating experience has shown that area radiation l
dose rates originate primarily from radionuclides in the pool water. During refueling L
and other fuel movement operations, pool water concentrations might be expected to increase somewhat due to crud deposits spalling from fuel assemblies and due to j
. activities carried into the pool from the primary system. Should dose rates above and j
around the cask pit perimeter increase, this change would be identified by routine
Docket Number 50e346 License Number NPF-3 SerialNumber 2550
. Attachment 2 Page 3 -
radiation surveys, and the appropriate radiological controls would be revised as required.
Radiation dose rates in accessible areas around the spent fuel storage and transfer zones l~
, have been conservatively evaluated based on realistic fuel parameters. Dose rates will l
remain within regulatory limits.' No changes to.the radiation zone designations i
described in the DBNPS Updated Safety Analysis Report (USAR) are anticipated.
Operating experience has also shown that there have been negligible concentrations of L
. airborne radioactivity in the spent fuel pool area.- No increase in airborne radioactivity
[
--is expected as a result of the expanded storage capacity.
The proposed change does not result in new surveillances which would require additional personnel entry into radiation controlled areas.
l With regard to potential non-radiological impacts, the proposed license amendment involves no increase in the amounts or change in the types of any non-radiological effluents that may-be released offsite, and has no other environmental impact.
l Based on the above, the DBNPS concludes that there are no significant radiological or non-radiological environmental impacts associated with the proposed license amendment.
Alternatives to the Proposed Action Since the DBNPS has concluded that the environmental effects of the proposed action are not significant, any alternatives will have only similar or greater environmental impacts. The principal alternative would be to not grant the license amendment. Since the environmental impacts of the proposed action are not significant, denial of the proposed license amendment would not significantly reduce the environmental impacts attributable to the plant.
Alternative Use of Resources I
o This action does not involve the use of resources not previously considered in the Final i
Environmental Statement Related to the Operation of the Davis-Besse Nuclear Power Station, Unit Number 1 (NUREG 75/097).
l Finding of No Sinnificant Imoact The DBNPS has reviewed the proposed license amendment against the categorical exclusion I
criteria of 10 CFR 51.22(c)(9) for an environmental assessment. As demonstrated in the proposed license amendment's SASHC, the proposed changes do not involve a significant hazards consideration, do not increase the types or amounts of effluents that may be released offsite, and do not increase individual or cumulative occupational radiation exposures.
Accordingly, the DBNPS finds that the proposed license amendment, if approved by the
Docket Number 50-346 License Number NPF-3 Serial Number 2550 -
' Attachment 2 -
Page'4 Nuclear Regulatory Commission, will have no significant impact on the environment and that no environmental assessment is required.
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