ML20010E079
| ML20010E079 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/24/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Hovey G METROPOLITAN EDISON CO. |
| References | |
| CON-NRC-TMI-81-047, CON-NRC-TMI-81-47 NUDOCS 8109030042 | |
| Download: ML20010E079 (2) | |
Text
DISTRIBUTION _
p UN 50-320 NRC PDR Local PDR o.,
TERA T P Q r/f NRC/TMI-81-047 AUG 2 41981 LBarrett Docket No. 50-320 AFasano
,y ' j, op' / g y
RConte f
M XH H Q 4XEKB Mr. Gale Hovey
((
t ey, ELD d
/iUG 2 7 Jggy[%
2 Licensing Assistant Vice President and
.f Director of THI-2 ACRS (16)
Metropolitan Edison Company.'c BSnyder u.' %m a ps 2
R. Weller P.O. Box 480 P
Middletown, PA 17057 s
G. Kalman M
J L. Gage
Dear Mr. Hovey:
N co4I
Subject:
Design Criteria for ' Recovery Facilities We have reviewed your design criteria for the Three Mile Jsi 2nd Unit 2 Recovery Facilities (135B7-2-601-100) and the Containment Recovery Service Building. Our specific comments are included below.
1.
Reactrr Building Integrity: The recovery technical specifications specify that " Primary containment integrity shall be maintained...".
Without analyzing each proposed evolution inside the reactor building (RB), it should.not be assumed that a temporary equipment hatch cover designed to withstand a 1 psi differential pressure (item 5.4.6.2 of your submittal) will provide adequate primary containment integrity for the full spectru:n of recovery operations inside the RB.
Each proposed evolution inside the RB should be reviewed on a case by case basis to evaluate the potential for causing an inadvertant RB pressurization and an appropriate level of containment integrity will oe assigned to each operation. We do not concur with the statement that "the CRSB serves no nuclear safety functions" (item 5.1 of your submittal). After removal of the equipment hatch the containment recovery service building (CRSB) will serve as a RB contamination barrier.
Prior to removing the equipment hatch, Section 3.6.1 of the Technical Specifications requires modification to permit operations without an operable containment airlock.
2.
Water used for flushing tihe reactor coolant system (RCS) should be of equal (or better) quality as that used for RCS makeup water (table 4.3 of your submittal).
3.
The upper limit on boron ' concentration for primary water and standby pressure control. tank water may be increased to the technical specification limit of 4500 ppm (table 4.3 of your submittal).
T
"'c'>
- sunwaur) 8109030042 810824 PDR ADOCK 05000320 onn)
P PDR
.......l..............l................
unc ron i m no so, anci "
OFFICIAL. RECORD COPY
I I
AUG 2 41981 Mr. Gale Hovey
-2 4.
Specifications for water used in the mini decay heat removal system should be supplied and the criteria for this water should be the same as for RCS water (table 4.3 of your submittal).
5 The dissolved gas concer.tration for water in the SPC surge tanks should be limited to less than 15 sec/kg (table 4.3 of your submittal).
If you have questions concerning the above comments, we are available for further discussions prior to your written response to our concerns.
Original signed by Lake H. B,m * +
Lake H. Barrett Deputy Program Director TMI Program Office cc:
See Service Distr ;bution List TQ..:,P.6 err,c r >.TMI:P TMI
="~ ~ >. R.Be,1, _,,, O m 3, y.,~ n.,,,,,..yB,a.,
.... 2. [./ 81 8/
oarr) 82-./.81 8/. ^./81
- on.mo,uncaoa4o c6VFHKeN3fLSE CORD COPY j