ML20125D718
| ML20125D718 | |
| Person / Time | |
|---|---|
| Site: | 05000130 |
| Issue date: | 08/09/1967 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20125A538 | List:
|
| References | |
| FOIA-85-54 NUDOCS 8506120449 | |
| Download: ML20125D718 (3) | |
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SATETt EVAIDATION BY 'INE DIVISION OF REACIDR LICDISING IN 'INE MATTDt OF, I
NOR'INERN STATES POWER C(HPANY f
PA'INFINDER A'ItMIC POWER P!Aff DOCKER NO. 50-130 PROPOSED CHANGE NO.15 i
i INI1t000CTION l
On July 28, 1967, Northern States Pcwor Cospany a quested authorization to n -
vise the Technical Specifications of Provisional Ope mting License No. DPR-ll pumuant to the previsions of Section 50.59 of the Cosmission's agulations.
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'!his change would pennit the storage of new Com II boiler and superheater fuel I
elements.
'the licensee mquests authorization for the following changes in Appendix A, Technical Specifications to DPR-ils In Section 14.9.10
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(1) It is a quested that the first sentence of this section:
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"'Ihe fuel handled or stoned as described in this section shall be limited i
to the fuel as described in these specifications."
4 be mplaced with the following:
"The fuel handled or stond as described in this section shall be limited to fuel as described in these specifications or as described in ACNP 67525."
(2) It is a quested that the third paragm ph of subsection (b):
"The maximum calculated flooded V,ff for the superheater stomge shall be less than 0.70."
be a placed with the followings i
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"'!he maximum calculated flooded K,ff for the superheater stomge shall be i
less than 0.80."
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(5061 g 9 850214 PAY 85-54 PDR
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(3) It is sepassted that the fifth peregraph of subosotian (b):
"The new fuel stesuge vault shall contain a mesdanse of 154 boiler elements and 550 supeshester elements. There shall be appresdastely in eneh 2 ;n each boiler element and appsesdastely 0.33 lbs. of 173 lbs. of UD i - % element."
'UO2 be suplaced with the fo11 M =3:
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"The new fuel stcruge vault shall contain a andansa of 154 boiler elements and 550 superheater elemente. These shall be apuesdastely in each Core I boiler element and,,.1-
--*ehr 0.33 173 1ho. of UD2
, Ibe. of UO2 in each Core I supesheater element. 1hese shall be appuesdnetely let 1bs. of in each Casu II boiler element and appresdastely 5.501ho. of in each Case II supesheater element."
'fhe ehenges considased here are necoseery to pennit the licenses to stese new Case II boiler and superheater fuel elements for the Pathfinder sweater in the esdsting fuel storage vault. Mditional will be requiswd to pensit awfueling the tweeter with Core II fuel and 1 he regnested at a later date.
MERESIG!
I the principal safety considerution for the new fuel storage is maintaining secure, should the fuel et orderly steswee, in an arrey ddah will ensure that F gg,tive margin to crit o
vault inadvertently become flooded, will leave a conserva ty.
We believe that the Forf ess than 0.80 by the appliment psovides a l
- sufficient and conservative massin to tiaality.
Secure, orderly fuel storage is maintained by pensitting stesuge of no more fusi elemente then the stosuge reeks are designed to asocomodate.
The licenses has calculated Fett or the fuel storage vault by considering both the f
boiler element arvey in the flooded vault and the supeshester element arvey in the -
flooded vault. In both cases the calculated F,ff is less then 0.80. 1hm storego rocks in the Pathfinder fuel vault are constructed so that appresdastely 8 inches are maintained between ad acent tiare of superheater elemente, 23 inches are maintained between adjacent double towe of boiler elemente, and most then 24 inches are maintained between supeshester fuel elemente and the nessest boiler fuel elements. We have asummined the situation Wuru both arneys aus present in the flooded vault and have concluded that, since the boiler and supushester elements are esperuted by seuw then two feet, coupling is pesoludedi thestfase, the limiting Fogg is the higher of the two arveys.
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We have concluded that the Proposed Change No.15 as set forth in this evaluation does not present significant hazards considerations not described or isplicit in the Final Safety Analysis Report, and that these is reasonable assurunoe that the health and safety of the public will not be endangered.
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t Donald J. Skovholt Assistant Director for Reactor Opesetions Division of Reactor Licensing Date August 9, 1967 J
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