ML19253B996
| ML19253B996 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 12/15/1972 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7911040005 | |
| Download: ML19253B996 (3) | |
Text
w.
i l'
Docket No. 50-289 DEC 151972 i
i M tropolitan Edison Company ATTN:
Mr. John G. Miller Vice President P. O. Box 542 Reading, Pennsylvania 19603 j
Centlemen:
The Regulatory staff's continuing review of reactor power plant safety l
indicates that the consequences of postulated pipe failures outsW of the containment structure, including the rupture of a main steam or feedwater line, need to be adequately documented and analyzed by licensees and applicants, and evaluated by the staff as soon as possible. Criterion No. 4 of the Comuniasion's General Design Criteria, listed in Appendix A of 10 CFR Part 50 requires that:
l
" Structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environantal conditions associated with normal operation, maintenance, testing and postulated accidents, including loss-l of-coolant accidents. These structures, systems, and components shall be appropriately protected against dynamic effects, including l
the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from, /ents and i
conditions outside the nuclear power unit."
1505 097 l
The previous version of the Commission's General Design Criteria also I
reflect the above requirements. Thus, a nuclear plant should be designed so that the reactor can be shut down and maintained in a safe shutdown condition in the event of a postulated rupture, outside containment, of a pipe containing a high-energy fluid, including the double-ended rupture of the largest pipe in the main steam and feedwater systems. Plant I
structures, systenn, and components important to safety should be designed I
and located in the facility to accommodate the effects of such a postu-lated pipe failure to the extent necessary to assure that a safe shut-down condition of the reactor can be accomplished and maintained.
i Based on the information we presently have available to us on the Three Mile Island Nucicar Station, Unit 1, we understand that main feed-water and steam lines pass through sep~arate compartments in the inter-mediate building anc' are located on a floor above the tutbine driven l
emergency feedwater pumps and electrical cabling for various engineered
}p safeguards equipment. From this it appears that some nodificaticus of the facility mey be necessary.
OFFICE >
I SURNAME >
DATE >
_ V Form AEC-5ts (Rev. 9-53) AECM 0240 e u s oove= w e%v >=%vmo o n cE. I972-466-984 7911040 N
i i
Metropolitan Edison Company !
l We request that you provide us with analyses and other relevant information i
needed to determine the consequences of such an event, using the guidance provided in the enclosed general information request. The enclosure represents our basic information requirements for plants now being i
constructed or operating. You'should determine the applicability, fe r the Three Mile Island Nuclear Station Unit 1, of the items listed in the enclosure.
If the results of your analyses indicate that changes in the design of structures, systems, or components are necessary to asoure safe reactor shutdown in the event this postulated accident situation should I
occur, please provide information on your plans to revise the design of your facility to accommodate the postulated failures described above, j
Any design modifications proposed should include appropriate consideration of the guidelines and rs quests for information in the enclosure.
i We will also need, as scan as possible, estimates of the schedule for l
design, fabrication, and installation of any modifications found to be necessary. Please inform us within 7 days after receipt of this letter l
vhen we may expect to receive an amendment with your analysis of this postulated accident situation for the Three Mile Island Nuclear Station I
Unit 1, a description of any proposed modifications, and the schedule estiestes described above. Sixty copies of the amendment should be previded.
i A copy of the Commission's press announcement on this matter is also i
enclosed for your 1x 3rmation.
Sincerely, J/O"M Chd by M:
Boyd l
} $. Giambusso, Deputy Director 3
for Reactor Projects l
Directorate of Licensing i
j
Enclosures:
i As stated I
i cc: See next page i
1505 098 I
b i
AD/Pbh _
Ms DD/RP j
omer > _Ewa,.2...
.k.....
PWR-2
?
MJ
- x ff d sumer >..HS.chieding........KKniel RCDAX5mng...
RBoy
..AGiambus so 12 /,1,3,,/,72,,,, _ _,,,12/n./72 12/ /[72 _
12/ 7/72 12/ /22 our>
Form AEC-318 (Rev.9 53) AECM 0240 o u s covenaus%r===rwo omte 1972 46 6984
.=s, i
l i
t Metropolitan Edison Company
- General Public Utilities Service Corporation cc:
j-ATTN:
Mr. Richard W. Howard Project Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 General Public Utilities Service Corporation ATIN:
Mr. Thomas M. Crinnnins, Jr.
Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Cerald Charnoff, Esquire Shaw, Pittman, Potts, Trowbridge & Madden 910 - 17th Str6at, NW Washington, D. C.
20006 Distributinn:
Local PDR Docket file RP Reading PWR-2 Reading SHanauer RSBoyd RCDeYoung i
DSkovholt i
FSchcoeder RMaccary DKnuth RTedesco j
HDenton PWR Branch Chiefs RKlecker OGC R0 (30 ACRS (18)
HSchierling AGiambusso i
MServied 1505 099 xxniel OFFICE >
< ~.
$URNAME >
I i
DATE >
Form AEC.3ie (Rev. 9-53) AECM 0240 e u s novan% ewr pai%rimo ones t 9 72-466-98 4