ML17326B198
| ML17326B198 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/19/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM AEP:NRC:06785, AEP:NRC:6785, NUDOCS 8602240382 | |
| Download: ML17326B198 (6) | |
Text
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4CCES STl5fVA FAC IL: 50-31 5 50-3 1 6 AUTH. NAME ALEXICHI M. P.
REC IP. NAME DENTONI H. R.
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RECULATOR1+hlFORNATION'ISTRIBUTION SEN (RIDE)
DOC.IIiITE: 357037 IB ROTARIIED: N5 '
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Donald C.
Cook Nuc lear Power Plant>
Unit 1I Indiana 05000315 Donald C.
Cook Nuclear Power P 1 anti Unit 2>
In d iana 05000316 AUTHOR AFFILIATION Indiana
& Michigan Electric Co.
REC IP IENT AFF 1 LIATION Office of Nuclear Reactor Reg u1 at ionI Director
( post -851 125 SUB JECT:
Summar 1 z es planned acti onsI p er 85121 9 meet ing I re Attac hments 1
& 2 to NUREG-0737> Sections II. B. 3
& II. F.
1> including past-accident samp 1 ing sos>
1 ocati on of main steam gas effluent radiation detec tors
& eb erl ine monitoring sos.
DISTRIBUTION CODE:
A046D COPIES RECEIVED: LTR ~ ENCL P SIZE:
TITLE:
OR Submittal:
TMI Acti on Plan R g mt NUREG-0737
& NUREQ-Obtcl0 REC IP IENT ID CODE/NAME P WR-A *DTS PWR-A EB P WR-A FOB P WR-A P SB REG FI INTERNAL: ADM/LFMB IE/DEPER DIR 33 NRR BWR ADTS NRR PWR-A ADTS T
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W I> wa Wza 4f 44j INDIANA 8 N ICHIGAN ELECTRIC COMPAN Y P.O. BOX 16631 COLUMBUS, OHIO 43216 February 19, 1986 AEP:NRC:0678S Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 NUREG-0737, SECTIONS II.B.3 and II.F.1 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
On December 19, 1985, Indiana 6 Michigan Electric Company held a meeting with your staff to discuss Technical Specifications for NUREG-0737,Section II.B.3 and II.F.1, Attachments 1 and 2.
The following is a brief summary of the actions we currently plan to take as a result of that meeting.
I.
Post-Accident Sam lin S stem (BASS):
After the NUS Corporation has completed their testing program, and a reevaluation of the PASS is completed, we will be submitting to your staff a complete detailed description of the PASS system relative to the requirements of the NUREG-0737,Section II.B.3.
II.
Location of the Main Steam Noble Gas Effluent Radiation Detectors:
Questions have been raised concerning the present locations of our main steam effluent detectors and whether they meet the intent of NUREG-0737,Section II.F.l, Attachment 1.
We are currently evaluating our position on this issue and will advise you accordingly.
III. Eberline SPING 3 and 4 Monitoring S stem:
At the present
- time, AEP and Eberline are in the process of developing a
technical information data package which will be submitted to your staff for review.
The purpose of this data package is to discuss the current Eberline system at the Donald C. Cook Nuclear Plant with respect to NUREG-0737,Section II.F.1, Attachment 1 for the following areas:
detector sensitivity/
- response, detector linearity, maximum range capability and acceptable range overlap between the low, mid and high ranges.
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Mr. Harold R.
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AEP:NRC:0678S IV.
Radiation Source Terms for the Main Steam S stem:
Source terms are being evaluated for the Steam Jet Air Ejector (SJAE) and the Gland Seal Condenser Exhaust (GSCE) systems.
After these source terms are fully developed, they will be submitted to your staff for approval.
V.
Continuous Sam ling:
Because of moisture problems in the SJAE and GSCE systems it is difficult to have continuous sampling that. is representative for iodine and particulates.
Therefore, an alternative
- method, which is more conservative, is being evaluated.
It is our intention to submit our methodology for sampling these two systems and)request,an exemption from continuous sampling of the SJAE and GSCE systems.
We currently anticipate submitting the above information no later than September, 1986. If our schedule should change significantly, we will advise you at that time.
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, MPA/cm M. P.
A xich Vice President Qg~g(~
cc:
John E. Dolan W.
G. Smith,.Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector Bridgman
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