ML17321A944
| ML17321A944 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/04/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17321A945 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-2.F.1, TASK-TM AEP:NRC:0856N, AEP:NRC:856N, GL-83-37, NUDOCS 8511120180 | |
| Download: ML17321A944 (7) | |
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'DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Planti Unit 1i Indiana 5
05000315 50-316 Donald C ~
Cook Nuclear Power Planti Unit 2i Indiana 8
05000316 AUTH NAME AUTHOR AFF ILIATION ALEXICHiiR.P.
Indiana 8 Michigan Electric Co ~
RECIP.NAME RECIPIENT AFFILIATION DENTONiH.R.
Office of Nuclear Reactor Regulationi Director
SUBJECT:
Apo)ication for amends to Licenses DPR 58 8 DPR"74ichanging Tech Soecs re installation of containment hydrogen monitors oer NUREG-0737i Item II.F. 1.6iGeneric Ltr 63"37 8
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 1.6631 COLUMBUS, OHIO 43216 November 4, 1985 AEP:NRC:0856N Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 CONTAINMENT HYDROGEN MONITOR TECHNICAL SPECIFICATIONS CHANGE REQUEST NUREG-0737 ITEM II.F.1.6 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This Technical Specifications (T/Ss) change request constitutes our response to NUREG-0737 Item II.F.1.6, Containment Hydrogen Monitors.
During the development of these T/Ss, an effort was made to adhere to the guidance provided in G.L. 83-37; however, several differences remain.
These differences and our analysis concerning significant hazards considerations are set out in Attachment 1.
The proposed revised T/Ss pages are included in Attachment 2.
We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at its next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(1),
copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. G. Bruchmann of the Michigan Department of Public Health.
Pursuant to 10 CFR 170.12(c),
we have enclosed an application fee of
$150.00 for the proposed amendments.
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Mr. Harold R. Dent AEP:NRC:0856N 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,
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M. P.
exichgS Vice President~ (f/["~
cm Attachments CC:
John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff G. Bruchmann NRC Resident Inspector Bridgman
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ATTACHMENT.1 TO AEP:NRC:0856N The guidance given in Generic Letter No. 83-37 states that:
"Two independent containment hydrogen monitors should be operable at all times when the reactor is operating in Power Operation or Startup modes.
LCO for these monitors should include the requirement that with one hydrogen monitor inoperable, the monitor should be re-stored to operable status within 30 days or the plant should be brought to at least hot standby condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
If both monitors are inoperable, at least one monitor should be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant should be brought to at least hot standby condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Typical surveillance requirements are provided in Enclosure 3."
We are proposing this T/Ss change to our current T/S 3/4.6.4.1 to include these requirements for both Units 1 and 2.
As required by Regulatory Guide 1.97, we have installed hydrogen monitors that have ranges of 0 to 30 volume percent hydrogen.
Because of this wide operating range, we are proposing to use nominal four and fifteen volume percent hydrogen as our sample gas for our CHANNEL CALIBRATION, rather than one and four volume percent hydrogen as suggested in Enclosure 3 to Generic Letter 83-37.
We believe this will provide us with a better calibration.
We believe the changes proposed in this letter are consistent with the intent of the NUREG-0737 guidance and with our system design.
In addition, since these changes constitute additional requirements that are not presently included in the T/Ss, we believe these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92.