ML19253B985
| ML19253B985 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/19/1977 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19253B981 | List: |
| References | |
| NUDOCS 7911020522 | |
| Download: ML19253B985 (6) | |
Text
-
- [
UNITED STATES NUCLEAR REGULATORY COMMISstON y
WASHINGTON. D. C. 20555 g
~.
METROPOLITAN ED! SON C0l1PANY g., j#
JERSEY. CENTRAL POWER AND LIGHT C0!1PA g PENNSYLVANIA ELECTRIC COMPAliY DOCKET N0. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICEliSE Anandment No. 34 License No, DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The application for amendment by Metropolitan Edison Company, A.
Jersey Central Power & Light Company, and Pennsylvania Electric Company (tne liccnsees) dated February 3,1977, as supplemented 21, 1977, complies with the standards and re-May 24 and July quirements 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 Comission; There is ressonable assurance (1) that the activities authorized C.
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1505'024 4911020 722
Accordingly, the licer.se is amended by changes to the Technical 1.
Specifications as indicated in the attachment to this license amendnent, and paragraph 2.C.(2) of facility Operating License No. DPR 50 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendr.2nt No. 34, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE UCLEAR REG'JLATORY CC'"'ISSIO" 7-6 t
Karl R. Goller, Assistant Director for,0perating Reactors Division of Crerating Reactors
Attachment:
Changes to the ~echnical Specifications Date of Issuance: December 19, 1977 O
e t
O re 1505 025
ATTACHi4Et!T TO LICENSE AfE!!DMEIT tl0. 34 F'.CILITY OPERATItlG LI:EtiSE f:0. DPR-50 DOCKET f!0. 50-289 Remove Pages Insert Pages 3-55 & 3-56 3-55 & 3-56 5-7 5-7 The changed areas on the revised pages are shown by marginal lines.
t e
a 1505 026 e
H;JU.I':0 0F..m: ATED FUEL 3,11 Atplicability Applies to the operation of the fuel handling building crane when within the confines of Unit I and there is any spent Puel in storage in the Ur.it 1 fuel handling building.
Objective To define the lift conditiens and allevable areas of travel vhen loads to be lifted and transperted with the fuel haniling tsilding crene are in excess of 15 tons or between 3000 lbs. and 15 tons or consist of irradiated fuel elements.
Sre ci fi cat i c:.
fuel elements having lesc than 120 days for decay of their 3.11.1 Spent irradiated fuel shall net be loaded into a spent fuel transfer cask in the shippirg cask area.
for aute=atically li=iting The key operated travel interlock syste:
3.11.2 the travel area of the itel har.dling building crane shall be i= posed whenever lcais in excess of 15 tens are to be lifted and transported with the exception of fuel handling bridge maintennnce.
The lovest surface of all leais in excess of 15 tens shal.' be admin-3.11.3 istratively litited to an elevation one foot or less above the concrete surface at the no inal 3LS ft-0 in. elevation in the fuel handling building.
Loads in excess of hook capacity shall not be lifted, except for lead 3.11.h testing.
Follovinc =odifications or repairs to any of the load bearing cembers, 3.11.5 the cranc shall be subjected to a tes't l'ft of 125 percent of its rated load.
3.11.6 Except as specified in 3.11.2 and 3.11.3 above, loads in excess of 3000 lbs. shall be administratively can'rclled so that they are handled at the lowest practicable elevation and so that the center of mass of the load is:
(1) maintained below elevation 348 ft.-0 in. or (2) maintained at such distance from the edce of a fuel storaga pool c.ntainino irradiated fuel that should the load be released and tip over (such that the long dim-ension of the load was substantially horizontal) in any direction, the center of nass of the load would be at least six feet from the edge of any pool containing irradiated fuel.
3.11.7 A spent fuel shippina cask shall not be pernitted in the Unit 1 Fuel Handling Building.
Bases This specification vill licit activity releases to unrestricted areas resulting frc: danace te spent fuel stored in the spent fuel storage pools in the postulsted When event of the drop;ir.g of a heavy load frc= the fuel handling building crane.
a loaded spent fuel trsnsfer cask is =oved out of the decontacination pit area and along the centerline of the spent fuel pool's vest vall to the receiving /
shipping area (Figure 9-13, Secticn 9), it has a potenti drop of L3 feet vni:h is 13 feet cranter than its design basis drop. An analysis 11 was perfor=ed assuang
.itire contents of ten fuel assemblies are sufficiently das-that the cash and its 1505 027 3-55 Amendment "o.
34
e of all noble gases and J
a6ed cs a result of dr.,, ping the cash, to allev the es assumed to be d:rectly to the atmosphere cad iodine 'in the gap.
This release ves The site boundary doses resulting frc= this accident to occur instantaneously.
are 5 25 R vhole body and 1.02 R to thyroid, and are within the limits specified in 10 CFB 100.
Specificatic: 3 11.1 requires that spent fuel, having less than 120 days decay post-irradiation, not be loaded in a spent fuel, trans fer cask in order to ensure that the doses resulting frc: a highly i= probable spent fuel trans fer cask drop would be within those calculated above.
Specification 311.2 requires the key operated interlock systen, which auto-
=atically li=its the travel area of the fuel. handling crane (refer to Figure 9-IcA, fuel shipping cank, Section 9) while it is lifting and transper-ing the spent to be i= posed whenever loads in excess of 15 tens are to be lifted and trer.s;;r ei fuel in stcra6e in the spent fuel stcrage pools in Unit '
while there is any spent This auto atically ensures that these heavy loads travel in areas where, in the unlikely event of a lead drcp accident, there vould be ne possibili y of this event resulting in any da: age to the spent fuel stored in the po:ls or doing an:.
fuel poc' e ~' "-e. As described unacceptable structural da age to the spent in Secticn 9 7.1.1, the shipping cask a ea is designed to withstand the drc; cf the.= pent fuel shipping cask frc an elevatten of 3L9 ft without un ac c ept at '.e datage to the spent fuel pool strteture.
Specification 3.11.3 ensures tha; +he lovest suriaee of any heavy load never gets eleva* ice in higher than ene feet ateve the ecnerete surface of the 3L8 ft-0 in.
the fuel handling building (ncsinal eleva',1cn 3L9 ft-0 in.) thereby keepin6 83-7 en ual'kely load drop accident within acceptable limits.
impact force frc:
Specification 3.ll.L ensures that the proper capacity crane hock is used for lifting and transporting leads thus reducing the probability of a lead drop accident.
Following =odificaticn er repairs, specificatien 3.11.5 ccdirms the load ratins of the crane.
l Specification.11.6 imp 0scs administrative linits on handling loacs weighing in excess of 3000 lbs. to prevent damage to irradiated fuel.
Handling loads of less thar. 3000 lbs. without these restr %. ions is acceptable because the cansequences of dropping loads in this weight range are comparable to those produced by the fuel handling accident
. considered in the FSAR and found acceptable.
1 Specification 3.11.7 prohibits the presence of a sper.t fuel cask in the L'ni Fuel Handling Building.
This prohibition will be retainet' until the !!RC has c on:l ude:-
completed its review of spent fuel cask handing operations at TMI-l an::
that such operations can be perforned safely.
W D h If (1)
IS AR, Supple:ent 2',- Part VII D
A a6J o
Amendnent ?!o. 34 3-"
1505 028
South En-Spen: Fuci Pool A Spent 1 Fool' B Dry Nev' Fuel of Fuel North End of Fuel South End of Fuel Storage Arca Transfer Handl ing building Handling building Fuel Handling Euildine Canal KS 496 ***
66 Fuel Assys 64
- 256 **
0.37 2.8 0.36 1.45 Cores
- includes one space for acco: odating a failed fuel detection NOTES:
con:ainer.
includes three spaces for acco::odating failed fuel containers, t
fuel s cra;e racks with a
- Spent Fuel ?oci E centains spent reduced center'-:c-cen:er spacing of 13 5/3 inches to in:rcase the stcrage capacity of the pool.
All of the fuel asse bly storage racks provided are designed to Scis:ic Class 1 criteria to the accelerations indicaced c.
belo :
Fuel Transfer Canal Fuel Handling Building Fuel Handli.c Building Spe :
in Reactor Building Dry New Fuel Storage Arca And Speqt Fuel Foci A Fuel Pool B 0.3S s Horis.
0.76 g 0.25 g Vertical 0.51 g
- The "B" pool fuel storage racks are designed using the floor responsa spectra of the Fuel HandlinS Building.
Fuel in the storage pool shall have a U-235 loading ecual f.
to or less than 46.3 grams of U-235 per axial centimeter of fuel assembly 9D
- 3
~
Q 1f A
013--
d4 23
. REFERENCES-(I) FSAR, Section 9.7 o-1505 029 34 Ac:endment lo.
5-7