ML17334B091
| ML17334B091 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/18/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:0773Y, AEP:NRC:773Y, NUDOCS 8705260425 | |
| Download: ML17334B091 (5) | |
Text
, )1 ACCESBI5N NBR:
FACi 50-315 50-316 AUTH. NAME ALEXICH~ M. P.
REC IP. NAME MURLEY, T. E.
REGULATORY FORMATION DISTRIBUTION SYM (R IDS) 870528)0425 DOC. DATE: 8?/05/18 NOTARIZED:
NO DOCKET ¹ Donald C.
Cook Nuclear Pouer Planti Unit 1.
Ind iana 5
05000315 Donald C.
Cook Nuclear Paver Plant.
Unit 2i Ind iana 5
05000316 AUTHOR AFFILIATION Indiana Zc Michigan Electric Co.
RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC concerns expressed in 870304 ltr re SPDB.
Update of issues discussed a+ 870223 meeting re SPDB lis+ed.
S Kramer informed that reactor coolant subcooling di splayed on SPDB as discrete variable.
DISTRIBUTION CODE:
A003D COP IEB RECEiVED: LTR ENCL SIZE:
TITLE: OR/Licensing Submittal:
Supp l 1
+o NUREG-0737(Generic Ltr 82-33)
NOTES:
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MB REQ FIL 01 EXTERNAL: LPDR NBIC NRR/DLPG/HFB RES DEPY GI NRC PDR TOTAL NUMBER OF COPIEB REQUIRED:
LT1 R 16 ENCL
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INDIANA8 NICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 AE5:NR0:0773Y Ma 18 1987 NUREG-0737 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos
~ 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ADDITIONALINFORMATION CONCERNING VARIABLES DISPLAYED BY THE SAFETY PARAMETER DISPLAY SYSTEM U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C 20555 Attn:
T.
E. Murley
Dear Mr. Murley:
This letter responds to your staff's concerns expressed in your letter dated March 4, 1987 on the Donald C.
Cook Nuclear Plant Safety Parameter Display System.
A meeting was held with Mr. J.
Kramer of your staff on February 23, 1987 to discuss the Safety Parameter Display System.
Specifically, we discussed three issues addressed in our letter AEP:NRC:0531K, dated September 26, 1985.
The following is an update of the status of these three issues:
Subcoolin Monitor At the meeting, we informed Mr. Kramer that reactor coolant sub-cooling is displayed on the SPDS as a discrete variable.
Although this indication is not read directly from the subcooling monitor, it provides an indication of subcooling which is based on the input from the highest incore thermocouple temperature.
The subcooling monitor indication is based on either the highest temperature of eight preselected incore thermocouples or on any one of the eight thermocouples as selected by the operator.
Steam Generator Radiation As discussed in the meeting, we do have the capability to detect main steam line radiation through monitors located on the power-operated relief valve (PORV) lines.
These monitors provide continuous monitoring of the radiation effluent release path when the steam generator PORVs are relieving steam.
Therefore, when the PORVs are relieving steam, the monitors provide one of the means addressed by EOP E-3 to determine which unisolated steam generator would be the source of a tube rupture.
8705260428 0 P003i5 PDR ADOCK 5
PD P
AEP:NRC:0773Y The outputs of the PORV line radiation monitors are displayed on radiation monitoring system displays.
One of these displays is located adjacent to the SPDS displays in the control rooms.
Radiation monitoring displays are also available in the technical support center and the emergency operations facility.
Since an operator working at a control room SPDS station can readily view the radiation monitoring information, we feel there is not a significant need to display the PORV line radiation monitors on the SPDS.
Containment Isolation As part of the Detailed Control Room Design Review (DCRDR) Program, we have determined the need for additional containment isolation indication in the control room.
The DCRDR schedule provides for installing the containment isolation signals for Unit 1 during the 1989 refueling outage and for Unit 2 during the steam generator replacement.
Once the isolation signals are available, we intend to develop a means of displaying containment isolation either on the SPDS or so that it will be visible to a person standing in th'e vicinity of the SPDS.
I This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.
. Ale ich Vice President cm cc:
John E. Dolan G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III Administrator
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