ML19345A504
| ML19345A504 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/20/1977 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19345A503 | List: |
| References | |
| NUDOCS 8011240029 | |
| Download: ML19345A504 (3) | |
Text
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.REFUELIilri 0PEPATIO::S MEES t
'3/4.9.6 SHIELD TA !!! CAVITY 'iA:11pULATOR CRA!1E OPERASILITY I
The OPERACILITY requirements for the manipulator cranes ensure that:
'1 the nanipulater crane and universal handling tool will be used for Ino)venent of control rods and fuel asserblies, 2) each crane and tool has I; sufficient load capacity to lif t a control rod or fuel assembly, and 3) the 9 core internals and pressure vessel are protected from excessive lifting
' force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPE!!T FUEL PIT The restriction on movenent of loads in excess of the nominal waight of a fuel assembly over fuel assenblies in the spent fuel pit ensures that
! in the event this load is dropped (1) the activity release will be limited J,
to that contained in a single fuel assembly, and (2) any possible distortion of the fuel in the storage tanks will not result in a critical array.
This assumption is consistent with the activity release assumed in the accident analysis.
Handling of the spent fuel pit building roof hatches for infrequent transfers of spent fuel racks by administrative control uill assura safe handling of
- the roof hatches.
The restriction of r.ovement of the spent fuel storage
' racks and spent fuel inspection stand over spent fuel ensuras that a rack or
. stand cannot be dropped on spent fuel. Dropping of a rack or stand from a taxinun height will not result in loss of integrity of the fuel pit ficor.
y Handling of the fuel handling equipment for infrequent maintenance by adninistrative control will ensure the safe handling of any fuel handling componants.
Handling of fuel casks over the spent fuel pit is not permitted until such time as !!RC has revier:ed and approved the spent fuel cask drop
^
evaluation.
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i3/4.9.8 C00LA'iT CI'!CULATI0'l i
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The requirement that the Shutdown Cooling System be in operation is
- consistent with the assumptions in the analysis of the boron dilution accident and prevents local variations in boron. concentrations, thus mininiaing the effects of an inadvertent boron dilution.
It 1so assures that sufficient cooling capacity is available to remove dec3y heat and maintain the water in the reactor pressure vessel below-140 F as required during the ~ REFUELI lG l:0DE.
3/ 4. 9. 9 C0:1 TAI l1:E:li PURGE FA:1 SHUTDOW:1 SYSTE:1 The OPERABILITY of this system ensures that the containnent purge fan can be shutdown upon detection of high radiation levels within the contain-ment.
The OPERASILITY of this systen is required 'to restrict the release of radioactive caterial fron-the containment atnosphere to the environment.
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.REFl!ELITi GPERATIO:lS CRA:!E TRAVEL'- SpE';T FL'EL PIT LI;1ITI:!3 C0"71TI'1:1 FOR OPERATIO:!
3.9.7 Except for the spent fuel pit building roof hatches, the spent fuel inspection stand, the fuel handling equipnent and the spent fuel racks, loads in excess of 900 pounds shall be prohibited from travel over the-spent fuel' pit.
APPLICABILITY:
llith fuel assenblies in the spant fuel pit.
ACTIO:!:
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.
SURVEILLA' ICE REOUIREi1E!!TS 4.9.7 Except for the spent fuel pit building roof hatches, the spent fuel inspecsion stand, the tuel' handling equipment and the spent fuel raci:s, loads in excess of 900 pounds shall be prevented frota traveling over the spent fuel pit by administrative control.
Spent fuel pit building roof hatches, the spent fuel inspection stand, and the fual handling equipment may only be handled in accordance with approved viritten procedures.
Spent fuel storaga racks and the spent fuel inspection stand shall.be prevented fro. traveling over spent fuel assemblies by administrative control.
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< 2.ua M U - t. V NRC DISTntBUTION roa Pl..f 50 DOCKET MATERIAL FHOM: Yankee Atomic Elect. Co.
DATE or oocUucNT TO: pl(C Westborough, Mass 01581 05-20-77 D. E. Vandenburgh.
oATt noctivco 05-24-77
%cTTra BNOT OR12 C o PROP INPUT FORM NUMBER OF COPIES RECE6VCo ObntciNAL QW4CLASSIFICo 3
S N s u & 0~
- ocoP, ENCLOSU RE ocScRIPTioN Furnishing proposed modification to Notorized 05-20-77 Appendix A of Operatin License, cons'isting'of illowing movement of the spent fqe1 inspection 2 pages stand and fuel handling equipment ofc.r th,e tpent j
fuel pit....
DO NOT REMOXg 2 pages ACKNOWLEDGED PLANT NAME: YANKEE R0WE
} T Q3 n ec I SAFETY FOR ACTION /INFORMATION pmrinn
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ASSIGNED /.D:
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L,.PAOLECT__l'AliAGEi(;
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PROJECT MANAGER:
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I INTERi4AL DIST RIBUTION
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[ REG FILE d SYSTEMS SAFETY PLANT SYSTEMS SIT 2 SAFETY &
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SCl!ROEDER BEHAILOTA dei 101i_&_EL'LLE" Z
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!!ANAUER SIIMET L OPERATIliG REACTORS SPANGLER IIARLESS PAWLICKI STELLO SITE TECll, l
PROJECT MANAGEMENT REACTOR SAFETY OPERATING 'IECll.
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BOYD ROSS
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Btrri.ER SITE ANALYSIS MELTZ
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