ML17324A957
| ML17324A957 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/20/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17324A958 | List: |
| References | |
| AEP:NRC:0433K, AEP:NRC:433K, NUDOCS 8606260352 | |
| Download: ML17324A957 (6) | |
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05000316 AUTH. NqNE AUTHOR AFFILIATION ALEXICH,H. P.
Indiana 0 Nichigan Electric Co.
RECIP. NAl'1E RECIPIENT AFFILIATION DENTON> H. R.
Office of Nuclear Reactor Regulation>
Direc tor (post 851125
SUBJECT:
Clarifies 830510 application to amend Licenses DPR-58 5 DPR 74> revi sing Tech Spec s re inseY vice insp 4c testing requirements> boric ac id trans fer pumps 8< aux iliarg feedu.a ter pumps. Revised Tech Specs encl.
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lNDl4N4 8 NlCHIG4N ELECTRlC CONP4NY P.O. 80X 16631 COLUM8US, OHIO 43216 June 20, 1986 AEP:NRC:0433K Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 CLARIFICATION TO OUR SUBMITTAL AEP:NRC:0433 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
Pursuant to discussion with your staff, this letter and its attachment are being submitted as a clarification to our'arlier submittal AEP:NRC:0433, dated May 10, 1983 regarding Inservice Inspection and Testing
. for the Donald C.
Cook Nuclear Plant.
The Technical Specification (T/S) pages contained in the attachment to this letter are the same pages that were submitted with our earlier submittal noted above, but are updated to the current amendment.
In addition to resubmitting these pages we are retaining the current T/S test
,frequency for inservice testing of pumps pending our submittal of additional information requested by your staff.
The T/S change request for pump test frequency pursuant to ASME Boiler and Pressure Vessel Code Section XI requirements will be resubmitted at a later date.
The request for change on the rest of the items remains unchanged from our AEP:NRC:0433 submittal.
This revision to the T/S change request has been reviewed by the Plant Nuclear Safety Committee (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at the next regularly scheduled meeting.
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.
860b260352 Sb0620 PDR ADOCK 050003l5 P
PDR I
Very truly yours Y. P. Alexich Vice President 1901
~l cm Attachments cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman
Mr. Harold R. Dento AEP:NRC:0433K bc:
J.
G. Feinstein/T.
R. Satyan-Sharma/P.
E. Infanger S.
H. Horowitz/T. 0. Argenta/R.
C. Carruth J. J.
Markowsky/S.
H. Steinhart/J.
A. Kobyra R.
W. Jurgensen R.
F. Kroeger M. L. Horvath
- Bridgman J.
F. Stietzel
- Bridgman C. A. Erikson J.
B. Shinnock D. L. Wigginton, NRC - Washington, D.C.
AEP..NRC:0433K AEP:NRC:0433 DC-N-6015.1 DC-N-6500.1 NRCD:0433.TRS
Mr. Harold R. Denton AEP:NRC:0433K Attachment No 1 to AEP:NRC:0433K This Attachment provides a summary description and listing of the changes being proposed in Attachment 2.,
These pages include the same change requests as our previous submittal but have been updated to include amendments issued since our initial submittal.
The Unit No.
1 Technical Specifications are being revised to reflect issuance of the new T/S No. 4.0.5 via Reference (2) of our letter AEP:NRC:0433.
The new section 4.0.5 incorporates the Inservice Inspection and Testing requirements of the ASME Boiler 6 Pressure Vessel Code Section XI for the Donald C.
Cook Plant, Unit No.
1 and is identical to the section with the same number in the Unit No.
2 Technical Specifications.
The proposed changes will replace the individual testing procedures of various components by a standard reference to Section XI of the ASME Code.
Some changes are being proposed to make the Unit 1 and Unit 2 Technical Specifications equal in content.
The T/S change requests for the boric acid transfer pumps and the auxiliary feedwater
- pumps, located on pages 3/4 1-13, 3/4 1-14, 3/4 7-5 and 3/4 7-6 for Unit 1 and pages 3/4 7-5 and 7-6 for Unit 2 have been withdrawn.
These changes will be resubmitted at a later date pending further evaluation.
In addition, we have withdrawn our request to use the test frequency specified in ASME Boiler and Pressure Vessel Code Section XI for pump testing requirements on Unit 1 pages 3/4 1-11, 3/4 1-12, 3/4 5-5, 3/4 6-10, 3/4 7-15 and 3/4 7-16 and will retain the 31-day surveillance frequency of the current T/Ss.
The attached T/S pages incorporate these changes.
Revised Pa es for Unit No.
Current Pa e No.
Section Revised 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 0-2 1-11 1-12 4-7 4-8 4-9 4-10 4-11 3/4 3/4 3/4 3/4 3/4 3/4 5-4 through 5-6 4-12 4-33 4-34 4-35 through 4-42 (Table 4.4-6) 4-43 through 4-48 Footnote deleted 4.1.2.3.1 4.1.2.4 4.4.5.0; 4.4 '.2 4.4.5.6.3, 4.4.5.2.c 4.4.5.3.b 4.4.5.a.s No change, added for continuity Table 4.4-1 3.4.10.1, 4.4.10.1 Deleted Deleted Renumbered Pages 4-34 through 4-40 4.5.2
- subsections rearranged
Mr. Harold R. Dento AEP:NRC:0433K Revised Pa es for Unit No 1
cont Current Pa e
No Section Revised 3/4 5-6a 3/4 6-10 3/4 6-11 3/4 7-15 3/4 7-16 3/4 7-17 3/4 7-18 Deleted 4.6.2.1 Intentionally left blank 4.7.3.1 Intenti,onally left blank 4.7.4.1 Intentionally left blank B 3/4 0-5 B 3/4 4-12 B 3/4 4-13 4.0.5
- this is a new page 3/4.4.10 Deleted Revised Pa es for Unit No.
2 Surveillance requirement No. 4.1.2.3.1 for the centrifugal charging pumps has been changed from 2405 psig to 2390 psig, to reflect the difference in volume control tank pressure in Modes 5 and 6 from that in Modes 1 to 4.
Current Pa e
No Section Revised 3/4 1-11 4.1.2.3.1