ML17179A547
| ML17179A547 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 10/27/1992 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17179A539 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9211030145 | |
| Download: ML17179A547 (2) | |
Text
MEMORANDUM FOR:
FROM:
SUBJECT:
John A. Zwolinski, Assistant Director for Region Ill Reactors Division of Reactor Projects - 111/IV/V Office of Nuclear Reactor Regul~tion Hubert J. Miller, Director Division of ReaGtor Safety, Region III REQUEST FOR TECHNICAL ASSISTANCE INTERPRETATION AND RESOLUTION OF REGULATORY GUIDE (RG) 1.91 AT QUAD CITIES, DOCKET NUMBERS 50-254 AND 50-265 (AITS 92-0641)
ENCLOSURE 7 Determine if the licensee complies with RG 1.97,.Revision 2 for the ~eutron flux monitoring instrumentation, the reactor level instruments, and the Moore Industries signal conditioners.
Four unresolved items remain open.
Un resolved* i tern {254/88027-01CDRS);265/88028-0lCDRS)): -Determine adequacy of the neutron flux monitoring instrumentation i ".I meeting the Category 1 requirements.
The licensee's position is to follow the BWR Owner's Group recommendations as stated during subsequent discussions with the.NRC, which indicated that further review by NRR was required.
Unresolved item C25~/88027-03CDRSl:265/88028-03CDRSll:
E~aluat~ and determine acceptability of the licensee analysis concerning the off-scale indication of the reactor le~el indicators 263-73A and 263-73B with th~ recirculation pumps'*
running as identified in the licensee's letter dated Dec~mber 9; 1991.
Based upon the added instrumentation and.discussions with NRR/SICB, further review and analysis by NRR is required.
Unresolved itein C254/88027-05CDRSl:265/88028-05CDRSll:
Evaluate and determine acceptance of ~he licensee's use of Moore Industries signal conditioners as isolators.
Maximum credible fault testing pf these devices was completed per Test Report CWE-3212P, Revision 2, dated November 4, 1988, copies of which were previously forwarded to NRR/SICB (Model SCT/0-1V/0-1V/24Vdc(STD).
Unresolved item C254/88027-06CDRSl:265/88028-06CDRSll:
Evaluate and determine acceptance of the licensee's use of Moore Industries signal conditioners as isolators.
Maximum credible fault testing of these devices was completed per Test Report CWE-3480, Revision 0, dated October 12, 1989, copies of which were previously forwarded to NRR/SICB ((Models SCT/4-20mA/4-20mA/117Vac(STD) and MVT /80-160mV /4-20mA/ll 7Vac(STD).).
--~.
9211030145 921027 PDR ADDCK 05000237 P
J. A. Zwolinski 2
Direct any questions concerning this subject to either George Hausman at (708) 790-5523 or Frank Jablonski at (708) 790-5555.
We consider this to be a Priority 2 item with a completion date of January 16, 1993.
Attachment:
Commonwealth Edison Letter dated December 9, 1991 cc w/attachment L. N. Olshan, NRR A. G. Hansen, NRR B. S. Marcus, NRR S. F. Newberry, NRR DCD/DCB(RIDS)
Riii e
Hausman 10/2-&/92 Riii Riii
. rr 11*,(<?Iv Jabl bnski LHasse 10/ib /92 10~ /92.
Hubert J. Miller, Director Division of Reactor Safety
- RIII
~-
Ring 10-/i1')92
.RI I I r
Martin lOf~\\ /92