ML17321A507
| ML17321A507 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/29/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17321A508 | List: |
| References | |
| AEP:NRC:05000, AEP:NRC:5000, NUDOCS 8504040304 | |
| Download: ML17321A507 (9) | |
Text
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'E REGULATO INFORMATION DISTRIBUTION LITEM (RIDS)
ACCESSION NBR 85040
$ 0300 DOC ~ DATE 85/03/29 NOTARIZED NO FACIL$50-315 Donald C.
Cook Nuclear Power Planti Unit ii Indiana 8
50-316 Donald C,
Cook Nuclear Power Plant~
Unit 2'i Indiana 8
AUTH ~ NAME AUTHOR AFFILIATION ALEXICHgM,P, Indiana L Michigan Electric Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTONiH,R>>
Office of Nuclear Reactor Regulationi Director V
P SUBJECT$
Forwards hydrogen control program scheduleiinfo r e. MARCH 2 code injut deck L "Hydrogen Combustion 8 Control. Analysis Assumptionsi" per 850206 meeting. Complete loss of offsite'ower for significant periods unlikely.
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INDIANA8 AllICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March 29, 1985 AEP:NRC:gf5gfgf0 Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 HYDROGEN CONTROL PROGRAM (10 CFR 50.44(c))
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
On February 6, 1985, personnel from the American Electric Power Service Corporation (AEPSC) and Battelle Columbus Laboratories (BCL) met with NRC staff, to discuss the D.C. Cook Nuclear Plant program for final resolution of the hydrogen control issue (10 CFR 50.44(c)).
As a result of the discussions, we committed to provide the following information for NRC staff review and approval.
MARCH 2 computer code input deck(s) applicable to the D.C. Cook containment and systems; A hydrogen combustion model inferred from available Nevada Test Site (NTS) data; and Justification for scenario selection Attachments 2 and 3 to this letter contain the requested information.
As a supplement to Attachment 2 we have included detailed information on the AEP grid system and the D.C. Cook substation.
This information shows that the offsite power system supplying the Donald C. Cook Nuclear Plant to be very extensive, making the occurrence of a complete loss of offsite power for significant periods of time highly unlikely.
For this reason we consider such events to be out of the scope of the hydrogen control rule promulgated in 10 CFR 50.44(c).
This completes phase I of our program.
As we discussed with your staff, we will begin phase II after you have completed your review of the initial conditions and assumptions submitted in this document.
A schedule for time required to complete phase II is included as attachment 1.
We understand that your review and approval of the schedule in Attachment 1 is what is required for compliance with 10 CFR 50.44(c).
Also, page 8 of Attachment 2 provides four key modeling assumptions.
Assumption 1 is based on documents such as NSAC 32, "Workshop on Hydrogen Burning and Containment Building Integrity,"
and experimental work done by the ice condenser utilities.
Assumptions 2, and 4 are based on review of preliminary Nevada Test Site data.
Assumption 3 is currently undergoing comparison to experimental data, and it is anticipated 8504040304 850329 PDR ADOCK 05000315 P
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1 Mr. Harold R. Dento AEP: NRC:P5$ PO once this comparison is completed, the value of 17.5 ft/sec given for flame speed may be readjusted.
It should be noted that in describing the MARCH model, we are only describing the code capabilities, not their final utilization.
As we discussed with your staff, we intend to use MARCH only for hydrogen source term and scoping tool.
The CLASIX code will be used for containment capability purposes.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.
. Al ich Vice President cc:
John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector Bridgman
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ATTACHMENT 1 TO AEP:NRC:HWPO HYDROGEN CONTROL PROGRAM SCHEDULE D. C.
COOK NUCLEAR PLANT
AEP:NRC:PSgPO SCHEDULE OF ACTIVITIES D. C.
COOK NUCLEAR PLANT HYDROGEN CONTROL PROGRAM ACTIVITY WEEKS AFTER START OF PROGRAM Review Proposed Program Approach With NRC Staff Review MARCH 2 Analysis Input With AEPSC Staff Perform Initial Set of MARCH 2 Analyses For In-Vessel Hydrogen Generation Define Effect Of Reactor Coolant System Vent Routing Define Effect Of Air Return/Hydrogen Skimmer System Fan Operability AEPSC And BCL Complete And Verify Input Decks for CLASIX Analyses (Three Accident Scenarios) 9, 11, 13 Assess Effects Of Spray Impingement And Related Factors On Glow Plug Igniter Effectiveness 15 Interim Program Review With NRC Staff 16 Determine If Possibility Of Local Detonations Exists; If So, Develop Detonation Loads For Dynamic Containment Analysis 23 Draft Report Issued By BCL AEPSC Review Of Draft Report Final Repoxt Issued By BCL 26 36 40 NRC Notified Of Final Resolutions Of BCL Work And Containment Dynamic Analysis 44
ATTACHMENT 2 TO AEP:NRC:HWPO ANALYSIS ASSUMPTIONS D. C.
COOK NUCLEAR PLANT