ML19210A480
| ML19210A480 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1969 |
| From: | Neidig R METROPOLITAN EDISON CO. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910300517 | |
| Download: ML19210A480 (6) | |
Text
- - ~ p r%
r%,
q w
y p
a
.,.x.
L ~ gy.
f"*"'
31strepe11tes Edisse Co.'
o^ " g g art o^n g g 1D2 ao n anns. F R.R. Neidig X
TO:
OR I G.
CC QTHILR 2 Morris 3 signed & notarised 5-20 69 & 40 conf *d cys ACTION NECESSARY O
coacuaarace O
care ^=swearo:
NO ACTsON NECESSARY O coaweav O
ev:
CLASSIF.4 PCGT OFFICE FILE GCEE2 50-289 U
.E. :
Lt E E N M T ~ M ren our Itr 1-7-69 "5""""
r*
o^"
arcrim av o^Te 5-27-59 d W/8 mya adion use of roller-me control rod drives....
6 re: out 1tr 2-5-69 & meeting 12-19 4$
- M 2.!!9* 5 "l* ** "*
- MRMti r
g g g -,
auctoSu=Es:
FgIL. REr0Ef... Summary of Factory Test
, M- = 12)
C' e
Remotor b1dging Fan Asscablies, Morris /Schmed./.3oyd I
=,
ae z. se.n dtd 5-9-49 D. Thompson
~
W/L-t-Essen 5 r; ar-Q [l()f '"'..
neue
- )
(3) cys holding far ACRS
- , _ _ g;g ( )
CGC
- ^ ' "' " " * " " "" '55 ' "
MAIL CONTROL FORMrcaug.n.3 l
- ............,....m..,,..i........
1491 106 7910300 5/ 7 /k
/
/
MflM
";" Lan -ams METROPOLl TAN EDISON COMPANY suosiotARY Of GENERAL PUBLicUTILITIESCORPORATION POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 May 9, 1969
': -. /..
, h'S s
y
\\'o United States Atomic Energy Commission N
~r Washington, D.C. 20545 k
'k'h }'
, ~
') h
' f p'9 d.kl
']
C 2
c Attention: Mr. Peter A. Morris, Director Division of Reactor Licensing
Subject:
Three Mile Island Nuclear Station Unit 1, Docket 50-289 (b)
U.S.A.E.C. Letter to Met-Ed dated January (a
7, 1969
Reference:
)
U.S.A.E.C. Letter to Met-Ed dat.ed February 5,1969 Gentlemen:
Regulatorjy file Op Reference (a) replied to the Met-Ed letter of December 10,1%8 which discussed the use of roller-nut control rod drives instead of the rack and pinion drives described in the Preliminary Safety Analysis Report. Reference (a) noted that certain points of difference appeared to exist between the two rod drive systems dnd requested further information with respect to:
(1) The capability to drive in a " stuck rod" equivalent to a 400 lb.
veight. This capability is discussed in Three Mile Island Unit 2 P.S.A.R., Docket 50-320, volume 2, Page 3-94, Section 3 2.4.3 1.1.h.
(2) The run speed of 30 inches / minute. This is discussed in T.M.I. 2 P.S.A.R., Docket 50-320, volume 4, Suylement 5, Page S5-1, Subject 1.0.
(3) The lack of a seal water injection. The roller nut rod drive design has no seals nor need for a seal water injection.
F 7k ge N
(4) A more indirect means of inferring rod position. This is A
discussed in T.M.I. Unit 2 P.S.A.R., Docket 50-320, volume 4, //
Je'$ W[~
8 Supplement 5, Pages S5-3 through SS-6, Subjects 4.0 and 5 0; and in volume 2, Page 3-99, Section 3 2.4.3 2.m.
C5 N $ #[,:
Q A/T 1491 107 5N o
co b
United States Atomic Energy Cormission Washington, D.C.
May 9, 1969 (5) The unidirectional clutch in the rack and pinion system denying upward motion with a rod withdrawal cignal. The following inform-ation vill be included in the Three Mile Island Unit 1 F.S.A.R.:
A system for inhibiting rod withdrawal in the event of a rupture in the system such as a unidirectional clutch or rod ejection latch has not been incorporated into the design. The analysis has proceeded to the peint where it is not considered that such a device should be required. Two years ago when the rack ( 7d pinion drive was being discussed sufficient calculatim ad not been made to determine whether a rod ejection inhibit device was required; accordingly, it was included in the rack and pinion mechanism. Upward motion of the roller nut drive due to a rup-ture in the pressure housing is inhibited by engagement of the roller nut and the lead screv while power is on the unit. When power is off the unit due to a low pressure scram following a major system break, analysis indicates that either a rupture in the housing or a loss of coolant accident vill not result in a positive reactivity addition to the core.
(6) Reanalysis of the startup accident, as a res' ult of faster nominal drive speed. This is discussed in T.M.I. Unit 2 P.S.A.R., Docket 50-320, Volume 4, Supplement 5, Page SS-1, Subject 1.0.
(7) Reevaluation of the rei ejection accident. This is discussed in T.M.I. Unit 2 P.S.A.R., Docket 50-320, volume 4,' Supplement 5, Page S5-1, subject 2.0.
(8) The quality assurance programs associated with the rod drives.
This is discussed in T.M.I.
Unit 2 P.S.A.R., Docket 50-320, Volume 4, Supplement 5, Page S5-2, Subject 3 0.
(9) Relationship of the control rod drive power system and position indication system as related to the control and protection system.
This is discussed in T.M.I. Unit 2 P.S.A.R., Docket 50-320, Volume 4, Supplement 5, Fages S5-3 and S5 4, Subject 4.0.
Reference (b) reviewed a meeting between Met-Ed and the A.E.C. Division of Reactor Licensing on Decerber 19,1%8 which was held to discuss issues not fully resolved during the construction permit review. Reference (b) further noted that certain design information should be made available to D.R.L. for review prior to filing the Final Safety Analysis Report in order to avoid potential delays in the operating license review, Response to the availability of design information for review for the items listed in reference (b) is as follows:
1491 108 United States Atomic Energy Commission Washington, D.C.
May 9, 1969 (1) Combined Seismic and Loss of Coolant Accident Loads Topical reports on the resultant stresses and defomation in the core and internals are in preparation. The report on the internals vill be available in the second quarter of 1%9, and the report on the core vill be available in the third quarter of 1969 Both will be filed with the A.E.C. as MW Topical Reports.
(2) Dilution System Controls Thr, design of the dilution system controls vill be available to Met-Ed in the second quarter of 1%9 as noted at the December D.R.L.
Meeting. Met-Ed vill forward by letter to the A.E.C. the 'IMI Unit 1 design upon receipt from MW.
(3) Failed Puel Element Detector A report on the scoping study is in preparation. This information vill be made available to Met-Ed in the second quarter of 1%9 Met-Ed vill then forward the report by letter to the A.E.C.
(4) Pressure Vessel Thermal Shock MW is planning to file a topical report on this subject with the A.E.C. by the end of May 1969 (5) R & D Items Updated information on the status and schedule for completion of these items is discussed in 'IMI Unit 2 P.S.A.R., Docket 50-320, Volume 4, Supplement 3 as follows:
(a) Xeron Oscillations Refer to Page 11.0 - Aa-1 through Page 11.0 - Aa - 3 A
MW Topical Report vill be issued in early 1970.
(b) Iodine Removal Spray Page 11.0 - AJ-l refera to the 'IMI Unit 1 P.S.A.R., Docket 50-289, Supplement 3, Answer to Question 17.4. A MW Topical Report will be issued in the second quarter of 1969 (c) Ther=al Hydraulics Refer to Page 11.0 - Ab-1 through 11.0 - Ab-2.
A MW Topical Report will be 1:, cued in the second quarter of 1969 1491 109
4-United States Atomic Energy Com:ission Washington, D.C.
May 9, 1969 (d) Internal Vent Valves Refer to Page 11.0 - Ae-1 through 11.0 - Ae-3 A B&W Topical Report vill be issued in the second quarter of 1969 (e) Fuel Rod Clad Failure Refer to Page 11.0 - Ac-1 through 11.0 - Ac 3 A B&W TSpical Report will be issued in early 1970.
(f) Self-Powered In-Core Detectors Refe'e to Page 11.0 - Ah-1 through 11.0 - Ah-2.
A B&W Topicel Report vill be issued in the second qur %er of 1969 (g) High Burnup Fuel Tests Refer to Page 11.0 - Ad-l through 11.0 Ad-2.
A B&W Topical Report vill not be filed since the tests are not needed to complete the safety evaluation of 'IMI Unit 1.
(6) Airplane Hardening of Critical Structures Infomation relative to the design of airplane hardened structures vill be available and forwarded by letter to the A.E.C. for review during July 1%9 (7) Reactor Building Fan Cooler Tests A preliminary report covering tests which have been or will be accomplished on the fan coolers is enclosed. The report covers the following tests: -
(a) Emergency Coil Test - A final report on the test vill be issued on or about July 1,1969 (b) Relief Valve Test - A final report on the test til be issued on or about July 1,1969 (d) Motor-Seal Winding Tests - completed.
(c
) Fan and Motor Tests - A final report will be issued by January 2, 1970.
1491 110
5
~
Uni +-d States Atomic Energy Comission May 9,1%9 Wa
- .gton, D.C.
Further reporting of the test results will be forwarded to the A.E.C.
by letter upon completion in accordance with the above schedule.
Very truly yours,
, 7 C t 'f L c c d -
R. E. KEIDIG j
Vice President J
REN:D Enclosure Sworn to and subscribed before me this 20th day of May,1969 b.
L
"..x Notary Public,/
Muhlenberg Township, Berks Co.
NoTagvs,"qt!C V',HLEN8!PC IDW:fSw:P, tE t*3 00' ' T.
,-~..a.-....
149i 111