ML17318A322
| ML17318A322 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/17/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| AEP:NRC:00256, AEP:NRC:256, NUDOCS 7910090795 | |
| Download: ML17318A322 (3) | |
Text
INDIANA II! MICHIGbN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 September 17, 1979 AEP:NRC:00256 Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos
. 50-315 and 50-316 License Nos.
G. Keppler, Regional Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler':
This letter supplements our letter of August 8, 1979 which responded to action item 1-B of IE Bulletin Nos.79-05C and 79-06C.
The attachment to this letter provides responses to the remaining action items of the bulletin.
Your letter of August 16, 1979 to us granted our request of August 8, 1979 for partial relief from the requirements of item 1-B.
We are members of the Westinghouse Owners'roup which is responding to the concerns of the Coranission resulting from the TMI-2 accident.
The present work scope encompasses previous NRC requests for information, NUREG-0578 and IE Bulletin Nos.79-05C and 79-06C.
Active discussions are now taking place between the Owners'roup, Westinghouse and the
- NRC, where issues contained in your requests are being evaluated.
Our response to the action items of IE Bulletin Nos.79-05C and 79-06C are in-line with the generic approach taken by the Owners'roup.
As such, we find our-selves proposing schedules to answer some of your requests.
We believe that this alternative approach will satisfy you and avoid conflicts and duplication of efforts.
Very truly yours, JED:em cc:
R.
G.
R.
R.
D.
C. Callen Charnoff S. Hunter W. Jur gensen V. Shaller - Bridgman ohn E.
Dolan Vice President
!!I9 II 0 {l907
- c.
fi Nid-October:
1 to 2 months from Mid-October:
3 to 4 months from Hid-October:
Guidelines which have been reviewed. by the NRC will be provided to each utility. Appropriate utility personnel associated with writing pro-cedures will meet with the Owners'roup Sub-committee on Procedures and Westinghouse to provide the background for revising their emerge'ncy procedures.
Plant specific procedures will be revised accordingly.
Revised procedures will be implemented and
)
operators trained.
Action Item 5:
Analyses related to inadequate core cooling and definition of conditions, under which a restart of the RCP's should be attempted will be performed by the Owners'roup.
Resolution of the requirements for the analyses and an acceptable schedule for providing the analyses and guidelines and procedures resulting from the analyses will be arrived at between the Westinghouse Owners'roup and the NRC staff.
Lon -Term Action:
As discussed in our response to item 2, we do not believe that automatic tripping of the RCP's is a required function based on the analyses that have been performed and submitted, and the guidelines that have been developed for manual RCP tripping.
We propose that this item be discussed with the NRC staff following their review of the Owners'roup submittal.
e ATTACHMENT TO AEP:NRC:00256 Action Item 1A:
On July 30, 1979 standing orders were issued to all operations personnel (licensed and non-licensed) to immediately trip the RCP s
upon a reactor trip and initiation of safety injection caused. by low reaction coolant system pressure.
Action Item 2:
A series of Loss of Coolant Accident (LOCA) analyses for a range of break sizes and a range of tine lapses between initiation of break and pump trip applicable to the 2, 3 and 4 loop plants has been performed by the Westinghouse Owners'roup.
A report (WCAP-9584) summarizing the results of the analysis of delayed Reactor Coolant Pump trip during srwll loss of coolant accidents for Westinghouse NSSS was submitted to Mr. J.
F. Stolz by Mr. Cordell Reed on August 31, 1979.
.The report provides maximum PCT 's and pump shutoff times for each break size'onsidered.
The report concludes that if the reactor coolant pumps are tripped prior to the reactor coolant system pressure reaching 1250 psia, the resulting PCT's are less than or equal to those reported in the Plant's FSAR.
In addition, it is shown generically that there is a finite range of break sizes and RCP trip times, in all cases 10 minutes or later, which will result in PCT's in excess of 2200oF as calculated with conservative Appendix K models..
In any event, the operator would have at least 10 minutes to trip the RCP's following a small break LOCA, especially in light of the conservatisms in the calculations.
This is appropriate for manual r ather than automatic action and agrees with the guidelines for termination of RCP operation presented in HCAP-9600.
Action Item 3:
The Westinghouse Owners'roup has developed guidelines which were submitted
'to the NRC in Section 6 of Appendix A of HCAP-9600.
The analyses provided as the response to item 2 are consistent with the guidelines in HCAP-9600.
No changes to these guidelines are needed for both LOCA and non-LOCA transients.
Action Item 4:
The Owners'roup effort to revise emergency procedures covers many issues, including operation of the Reactor Coolant Pumps.
The action taken in response to item 1 is sufficient as an interim measure and no inn~ediate need exists for changing our emergency procedures to include the tripping of the Reactor Coolant Pumps.
The expected schedule for revising the
- LOCA, steamline break and steam generator tube rupture emergency procedures by the Owners'roup is the following: