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JUL 211971 Docket Nos. 50-352 and 50-353 Philadelphia Electric Company ATTN:
Mr. Vincent P. McDevitt Vice President and General Counsel 1000 Chestnut Street Philadelphia, Pennsylvania 19105 Gentlemen:
On the basis of our review of your Preliminary Safety Analysis Report for the Limerick Generation Station, we find that the design of the main steam lines and the piping concepts for the low pressure coolant injection system and the high pressure coolant injection system could be improved to provide added safety margins. We request that you consider the incorporation of these improvements, as discussed in the succeeding paragraphs, in your design of Limerick, and inform us promptly of your conclusions.
If you intend,to modify the Limerick design to provide these improvements, the modifications should be described in an amendment to the PSAR.
In accordance with your current commitments, the main steam lines (MSL) piping from the reactor pressure vessel out to and including the outermost isolation valve will be designed, fabricated, and inspected to the requirements of Class I (seismic) and (AEC) Quality Group A.
The main steam lines from the outermost isolation valve up to but not including the turbine stop valve are classed as (AEC)
Group B.
To provide additional protection against seismic-induced failure of the main steam lines, the MSL segment from the outermost isolation valve up to and including the turbine stop valve could be designed to the same seismic standard as the remainder, namely, Class I (seismic).
The low pressure coolant injection system (LPCI) currently is designed to function following proper selection and opening of an injection valve in the line to the unbroken recirculation line.
Since currently there is a single LPCI line to each recirculation loop, the failure of the injection valve on the line to the unbroken recirculation line would negate operation of the LPCI system.
To eliminate this single failure problem and to attain greater margin in the capability of the 8709240472 870921 f
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Form AEC-Sts (Rev 9.$3) AECM 0240
- v. s. GOVERNMENT PRINTING OFFICE :1970 O. 406-34a
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total emergency core cooling system (ECCS), the LPCI system could i
l incorporate four separate and independent paths to deliver cooling water inside the core shroud of the reactor vessel.
The high pressure coolant injection system (HPCI) currently is designed to admit cooling water to the downcomer region of the reactor vessel via the feedwater line. Improvement of the core cool-ing capability of the HPCI system can be achieved by routing the HPCI line to the core spray sparger line. The HPCI system core cooling capability can be improved further by increasing the HPCI steam turbine operating capacity, thereby increasing the RPCI cooling j
water flow rate. The result of these HPCI system changes vould ex-tend the small break gegitac for which no rod perforations are expected to occur, from 0.2 ft' to 2.0 ft2, according to GE.
t Please contact us if you desire additional discussion or clarification of these improvements.
Sincerely, SHgInsi slped by I
Petw L ments Peter A. Morris, Director Division of Reactor Licensing cc: Mr. Richard Mulford Philadelphia Electric Company 1000 Chestnut Street Philadelphia, Pennsylvania 19105 n
(See attached for distribution)
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3 CONSULTING EWUNEEMfMG 6EAYpCES I-1514 CfVit, fl.Ctr#&.vWG DU:LOttto UfipsM ILLl4C 4 C1f.Cl 27 hly 1971 PRELIMINARY $AFETY ANALYSIS REPORT FGt I
i LIMERICK GEIERATING STATICN UNITS I AND 2 MlILADELPHIA ELECTRIC C0tPANY AEC Docket Nos. 50-352 and 50-353 by T
j N. N. Noteserk and W. J. Hall Af ter our revlaw of the PSAR, including Amendments through No. 7 I
and Supp%nts throup No. 5, it,Is believed thet the design of the Limerick Genergttng Station Units I and 2 can be constdere; adequate in rasms of t;
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provision for safa shutdown for a Design Bests Ea. :hquake of 0.12g anxtuun j
. hor:4antal ground acceleration, aM capable otherwise of withstanding the ettests cf an Operating Sasts Earthquake of half thle Intensity
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Ou; revlow was based on considerst!co, eeong other things, of the design criteria and ecsults of the analysts presented by the aoolicant for the found6tions, selsmic responso, damping factors, selsmic analys!s of structures, selsmic analysts of pfpfng, reactor Intsreals, equipment, and critical Items v,
of control and Instrumentation.
We believe the procedures used in the design and analysts are In
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accord with the state of the art.
It is car conclusfon that the design incorporates an acceptable range of margins of safety for.the hazards considered.
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l DOCXET 1:05. 50-352 CD 50-353 f
FWSCIAL MALYSIS I
l (dollars in millions)
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Ca16ndar_Yany Ended Deft.;dgr,,,j,1,,,
122L 1969 JL L
1.ong-term debt
$1,019.8
$ 348.7 778.7 Utility plant (net) l 1,9 72.1 1,674.4 1,459.4 tatio - debt to fixed plant
.52
.51
.53 Utility plant (net) 1,9 71.1' 1,674.4 1,459.8 Capitalization 1,877.9 1,577.9 1,393.1 Ratio of net plant to capitslisation 1.05 1.06 1.05 Ot.m,*.3midwre
- equaty -
858.1 729.2 614.4
-l total aseats 2,091.9 1,776.1 1,553.6
- A4 Proprietary ratio
.41
.41 40 Ny$
Earnings available to cessa squity 59.4 56.4 61.9 5 4 Cramon equity 664.4.
600.5 S25.7 Este. of earnings as common equity 9.01 9.7%
11.6%
Not income 68.4 64.3 65.6 i
Stockholders' equity 858.1 729.2 614.4 Rate of earnings on stockholder' egelty 8.01 8.8%
10.7%
Net income before interest 126.4 109.3 102.4 Liabilities and ca,, ital 2,091.9 1,776.1 1,553.6 tate of earnings on total investass :
6.01 4.1%
6.6%
bt income testore L.?-**st '
126.4 109.3 102.4 4
Intr,i.
t :n tr -oern, debt a
50.3 38.2 33.4 po, of tl.nas interest (. ton 8-term.) sarned 2.5 2.9 1.0 g"
Het intoas 68.4 64.3 45.4
% ral revenues
$23.1 448.5 415.4 tie M a retit
.1
,14
.16 T.tal utisity epurating expenses J76.7 339.2 313.0 tw al utill.ty cperating rewnues 504.4 440.5 405.2 Operating ratv,
.79
.77
.77 Utility piret (stoca) 2,521.6 2,186.6 1,951.2 Utility r,s. orating tevenues 504.4 440.5 405.2 Ratio of plant investsent to revenuse 5.0 5.0 4.8 4
1970 Casitelisation:
Mat
% of Total 1969 hnt
_ f. of Total 1,ong-term debt
$1,019.8 54.3%
$ 848.7 53.8%
Preferred stock 193.7 10.3 128.7 8.2 Comisco stock & surplus 664.4 J5.4 600.5 38.0 i
Total M
J22aB EEla2 100.E
!bedy's tc.nd Ratings: First mortgage Ana E.1
' pun and Bradstraat Credit lating 541 3 &c
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AUG 3 1971 Docket (2) v BWR-1 D
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Docket Mos. 50-352 R. S. Boyd l
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and 50-353 i
Dr. Spencer H. Bush Chairman, Advisory Committee on Reactor Safeguards l
U.
S. Atomic Energy Commission I
Washington, D. C.
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Dear Dr. Bush:
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I copies of the following are transmitted for 16 the Committee:
review by Philadelphia Electric Contpany (Limerick Generating Station Unita 1 & 2)
- 1. Amendment No. 10, dated 7/30/71;
- 2. FEC letter dated 7/30/71 submitting information in response to DRL letter on emergency cere cooling.
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i Sincerely,
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- -/M/N Peter A. llorris, Director Division of Reactor Licensing
Enclosures:
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