ML20073Q051
| ML20073Q051 | |
| Person / Time | |
|---|---|
| Site: | LaSalle |
| Issue date: | 04/25/1983 |
| From: | Schroader C, Schroeder C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM 6437N, GL-83-02, GL-83-2, NUDOCS 8304280126 | |
| Download: ML20073Q051 (3) | |
Text
"
/^N Commonwealth Edison
[
~
) One First Nationit Pina. C_ icago, Ilknois h
i
(,-} Addr;,ss R: ply to: Past Office Box 767 Chicago, !!!.nois 60690 April 25, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Unit 1 NUREG 0737 Technical Specifications NRC Docket No.-50-373-Reference (a):
Darrell G. Eisenhut Generic Letter 83-C2 dated January 10, 1983.
Dear Si :
Reference (a), which was received on January 25, 1983, requested that Commowealth Edison Company "..-review your facility's Technical Specifications to determine if they are consistent with the guidance provided..." and that we "... respond within 90 days of the receipt.of this letter."
The purpose of this letter is to provide you with the results of this review.
Commonwealth Edison Company has completed its review of Reference (a) and has determined that no changes in the LaSalle County Station Unit 1 Technical Specifications are required at this time.
An item by item review of Reference (a) is provided in the attachment.
To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.
In some respects y
these statements are not based on my personal knowledge but upon information furnished by other Commonwealth Edison employees. Such information has beer, reviewed in accordance with Company practice and I believe it to be reliable.
If there are any further questions on this matter, please contact this office.
Very truly yours, 0^1Ak,,,,io WI B304280126 830425
'^
C.
W. Schroeder PDR ADOCK 05000373 Nuclear Licensing Administrator P
- PDR, cc:
NRC Resident Inspector - LSCS
-6437N.
L.
ATTACHMENT 1.
STA TRAINING-(I.A.l.153) a).
STA (SCRE) duties are delineated in Technical Specification 6.1.C.6.
b)
NRC has accepted training and qualification requirements in LSCS SER.
2.
LIMIT OVERTIME (I.A.I.3) a)
Technical Specifications (T.S.) 6.1.C.7 meets this item.
3.
DEDICATED HYDROGEN PENETRATION (II.E.4.1) a).LaSalle has dedicated penetrations in containment for post-accident combustible gas control.
b)
NRC has accepted LaSalle's system per LaSalle SER.
4.
CONTAINMENT-PRESSURE SETPOINT-(II.E.4.2.5) a)- No action required as per this item in Generic Letter No. 83-02.
5; CONTAINMENT' PURGE VALVES (II.E.4.2.6) a)
NRC has accepted LaSalle's interim position on this item as reflected in LaSalle SER supplement 1.
b)
T.S. 3.6.1.8 reflects this position.
c)
Accident qualification of the purge valves is pending on the completion of review by NRC of the data submitted by CECO.
~ 6.
RADIATION SIGNAL ON PURGE VALVES (II.G.4.2.7) a)
No action required per this item in Generic Letter No. 83-02.
7..
REPORTING SV AND RV FAILURES AND CHALLENGES (II.K.3.3)
-a)
LaSalle meets this item in T.S. 6.6.A.5 which requires challenges be reported in the monthly report.
'. 8.
RCIC RESTART-AND RCIC SUCTION (II.K.3.13 II.K.3.22) a)
License conditions 2.C.30.j and 2.C.30.n require completion prior to restart after 1st refuel.
9.-
ISOLATION OF RCIC MODIFICATION-(III.K.3.15) a)
License condition 2.C.30.k requires completion prior to restart after 1st refuel.
10.
INTERLOCK ON RECIRCULATION-PUMP-LOOPS-(II.K.3.19) a)
This does not apply to LaSalle because LaSalle has jet pumps.
11.
COMMON REFERENCE LEVEL (II.K.3.27) a)
LaSalle meets this item, Reference Figure B 3/4 3-1 in LaSalle Technical Specifications.
12.
MANUAL DEPRESSURIZATION-(II.K.3.45) a )-
No action required on this item per Generic Letter No. 83-02.
F l'
-6437N l
l i
l-L!