ML19260A099
| ML19260A099 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/08/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19260A098 | List: |
| References | |
| NUDOCS 7910290718 | |
| Download: ML19260A099 (4) | |
Text
_.
DISTRIBUTION:
April 8, 1977 Docket v NRC PDR Local PDR ORB #$ Rdg.
Docht No.: 50-289 VStello KRGoller TJCarter Attorney, OELD OI&E(3)
RWReid Metropolitan Edison Company GZwetzig ATTH: Mr. R. C. Arnold Vice President - Generation
. RIngram DEisenhut P. O. Box 542
.TBAbernathy Reading, Pennsylvania 19603 JRBuchanan Gentlecen:
ACRS(16)
Gray File t htter dated February 3,1977, you requested amendment of Operating License No. DPr.-50 for Three Mile Island Unit No.1 (THI-1) to pemit an increase in the storage capacity of the spent fuel pool.
Based on our review of your request to date, we have detemined that additional information is needed in order to complete our review. The specific infomation needed is listed in the enclosure.
Since you have asked for an early.detemination of the acceptability of your proposal, you are requested. to submit tne information listed in the enclosure as scon as possible.
Sincerely,
? f.,
Robert W. Reid, Chief Operating Reactors Branch 14 Division of Operating Reactors
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page rf N N I,n 0lUlk ORBb: DOR C-OR"B#k: DOR o,,,c.,
n GZwetzig:dn RWReid
//
4/7/77 4/i'/77 NRC FORM 318 (9 76) NRCM 0240 W u.a.oovannuanveninvins or,ics.ieye.. 4 4 89102907/7
Metropolitan Edison Company cc:
G. F. Trowbridge, Esq.
Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 GPU Service Corporation Richard W. Heward, Project Manager Thomas M. Crimmins, Jr., Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Street Johnstown, Pennsylvania 15907 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonderry Township RFD #1, Geyers Church Road Middletown, Pennsylvania 17057 Miss Mary V. Southa-d, Chainnan Citizens for a Safe Environment P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17126 1479 317
THREE MILE ISLAND NUCLEAR STATION UNIT 1 SPENT FUEL PCOL MODIFICATION REOUEST FOR ADDITIONAL INFOPl'ATION 1.
Provide a detailed su==ary of the stress margins due to the increased loading of the fuel pool walls and floor for the critical load co=binations. Include a discussion of the possibility of shear failures in the areas of contact of the
~
rack supports with the floor and walls. Compare numerically these results to those for the previous rack structure.
2.
Provide the components of the stress value given in Table 5-2 for load combination "d" (as defined in Section 5.1.2) at grid beam location.
3.
Provide justif' cation for neglecting any a=plification of the seismic loads, transferred to the rack analyzed, due to the flexibility of the fuel cans in the adjacent racks.
4.
What has been the amount of solid wastes shipped from the plant in the last year?
5.
On page 3-4 of your sub=1ttal of February 3,1977, you sta:e that it is "i=possible" to predic: the a=ount of waste generated fro: :he precoa filter. If the volume cannot be "upperbounded", there is no basis for you or us to reach conclusion that the volu=e is negligible.
It is requested that you reevaluate the firs: paragraph of p. 3-4, dis-cussing the projected frequency of operation of the filters, the basis for their replacenent, the cubic feet of powdered resin used r precoat the filters and an esti= ate of the volu=e of solid vaste presen:1y a:-
tributable :o the SF? operations.
o.
What has been the release of rsdioactive noble gases and tri:1u: fro the SFP building in the last three years? Wha: is the expec:ed increase in the release of radioac:1ve noble gases and critiu= fro = the facility due to the SFP :odification?
7.
What is the weight of any =aterial (e.g., racks) that will be re=oved frc= :he SFP due to the modification? Wha: vill be done with this
=aterial?
1479 318
~
2-8.
Provide a discussion of increase in occupational =an-re exposure to personnel in the spent fuel pool area fre: radionuclide concentration in the Spent Fuel Fool due to the expansion of the capacity of the pool including the following:
(a)
Identify the principal radionuclide and their respective concen-trations in the spent fuel pool found by ga==a isotopic analysis during all operations.
Identify the sa=ple with respect to a specific operation (i.e., refueling, fuel handling, etc.).
(b) Provide an esti= ate of the man-rs= exposure that will be received during removal of the old racks and installation of new ones.
(c) Provide an esti= ate of the dose rates above the spent fuel pool fro = the concentrations of the radionuclides identified in (a) and the conco=icant occupational exposure, in annual =an-re=, due to all operations associated with fuel handling in t'ie spent fuel pool area.
Describe the i= pact of the proposed modifi-cations on :hese esti=ates.
Include in your analysis the expected exposure fro more frequent changing of the de=iner-ali:er resin and filter cartridges.
Durin[.the first refueling, 56 fuel asse=blies were transferred into 9.
the SFP. The sub=ittal stated that during the current refueling, 48 fuel asse=blies will be replaced. The submittal infers on p. 5-3 that on the average, you plan to replace 52 fuel assemblies per year.
Based on your current fuel =anagement plans, discuss :he projected refueling schedules, including the nu=ber of fuel asse=blies that will be transferred into the SF? at each refueling.
- 10. The sub=1::al (p. 5-3) states tha: the replace =en: cost of energy aad capacity would be approxi=a:ely $159 =1111on per year. Discuss whe:her reserves are such that replacenent pcwer for TMI-l would likely be available within the General Public Utilities Corporation System or fro = other utility systa=s af ter 1980.
If TMI-1 were forced to shut down due to lack of. storage space for spent fuel, discuss the source and cost of replacement pcwer if syste: reserves are not expected to be adeque,te without TMI-1.
If TMI-l were to be shut dcwn, there still would be certain costs associated wi:h the facility such as interest on invas:=ent, physical protection, etc.
apart fro = the costs for replace =ent power. Provide an esti= ate of the costs associa:ed with =aintaining !MI-l in a " shutdown" condition.
- 11. Discuss the nu=ber of spent fuel asse=blies that could be i=pacted in the proposed compact arrange =ent by the cask and associated lifting gear if :he cask and lifting gear should tip and fall while in or near the spen: fuel pool.
1479 319
.