ML17179A546
| ML17179A546 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Point Beach  |
| 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 9211030137 | |
| Download: ML17179A546 (2) | |
Text
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OCT 2 'l 1992 MEMORANDUM FOR:
John A. Zwolinski, Assistant Director for Region III Reactors Division of Reactor Projects - 111/IV/V Office of Nuclear Reactor Regulation FROM:
Hubert J. Miller, Director Division of Reactor Safety, Region III
SUBJECT:
REQUEST FOR TECHNICAL ASSISTANCE.
- INTERPRETATION AND RESOLUTION OF REGULATORY GUIDE (RG) 1.97 AT POINT BEACH DOCKET NUMBERS 50-266 AND 50-301 (AITS # 92-0640)
ENCLOSURE 6 Determine if the licensee complies with RG 1.97, Revision 2 for isolation of Foxboro H-Line instrumentati~n and for th~ unique identification of control room instrumentation.
Two open items remain open.
Open item C266/910lO~OlCDRSl: 301/91010-0lCDRSll:
Evaluate and determine acceptance of the licensee's lack of qualified isolation for Foxboro H-Line instrumentation at computer and control loops. This item remains open pending NRR review and acceptance of the licensee's submittal dated July 5, 1991.
Open item C2S6/91010-03CDRSl: 30l/91010-03CDRSll:
Determine the adequacy of the licensee's method of implementing RG 1.97, section C.l, paragraph 1.4.b, which addresses equipment identification. The licensee has not uniquely identified any RG 1.97 instruments as required by RG 1.97. Paragraph 1.4.b
- states, "The instruments designated as Types A, B, and C and Categories l and 2 should be specifically identified on the control panels )o that the operator can easily.di~cern that they are intended for use under accid~nt conditions.~
The submittals dated July 5, 1991, and July 29, 1992, state the licensee has
. installed post-accident monitoring {PAM) panels in the control room, where
. essentially all of the indicators mounted on these panels are used for.PAM.
As a result, the licensee feels that there is.no need to uniquely identify each indicator.
In addition, on the main control boards {MCBs), where the indicators for a RG 1.97 variable do not meet RG 1.97 requirements, labels are installed on the non-qualified indicators. The RG 1.97 qualified MCB indicators are not labelled. The licensee's justification for this method was to maintain the desired neat and clean appearance of the MCBs and to avoid.
potential operator confusion due to cluttered MCBs.
It is our position that the licensee's method of equipment identification meets the' intent of RG*- L97;' however ~
0"durfng *dlstussforis with -Mr*~ *s-arry~'Mifrcus of NRR/SICB, it *was determined that further review by NRR was required.
9211030137 921027 PDR ADOCK 05000237 P
OCT 2 7 1992 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.
Hubert J. Miller, Director Division of Reactor Safety_
Attachments:
- 1. Wisconsin Electric Power Company Letter NRC-91-064 dated July 5, 1991
- 2. Wisconsin Electric Power Company Letter NRC-92-083 dated July 29, 1992 cc w/attachment:
R. B. Samworth, NRR A. G. Hansen, NRR B. S. Marcus, NRR S. F.. Newberry, NRR DCD/DCB (RIDS)
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