ML17317B076
| ML17317B076 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/04/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17317B077 | List: |
| References | |
| AEP:NRC:00117, AEP:NRC:117, NUDOCS 7904130216 | |
| Download: ML17317B076 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:7904130216 DOC ~ DATE: 79/04/04 NOTARIZED! YES DOCKET FAC IL:
ONALD C ~
COOK NUCLEAR POI'lER PLANT p UNIT 1 g INDIANA 8 05000315 3
ONALD C
COOK NUCLEAR POAKR PLANT UNIT 2t INDIANA 5 05000316 AU
~ i AUTHOR AFFILIATION OOLANeJ ~ K'NDIANA 8 MICHIGAN POWER CO ~
RKC IP ~ NAME RECIPIENT AFFILIATION OENTONi H ~ R ~
- OFFICE OF NUCLEAR REACTOR REGULATION
SUBJECT:
FORVIARDS AMEiVO 83 TO FSAR ~
DISTR IBUTIOiV COOK ~
A001S COPIES RECEIVED'LTR + ENCL +~
SIZK2 TITLEe GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC NOTES!
RECIPIENT ID CODE/NAME ACTION!
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1 1
2 2
1 1
1 1
1 1
1
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1 1
1 16 16 RECIPIENT ID COOK/NAME 02 NRC PDR 14 TA/EDO 16 AO SYS/PROJ 18 REAC SFTY BR 20 EKB 22 BRINKMAN 04 NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 TOTAL NUMBER OF COPIES RKQUIRKOo LTTR 38 ENCL 38
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INDIANA IL MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 April 4, 1979 Afp:NRC:00117 Donald C.
Cook Nuclear Plant Units No.
1 and 2
Dockets No. 50-315 and 50-316 License No.
DPR-58 and DPR-74 FSAR Amendment No. 83 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter transmits to your office forty copies of Amendment No.83 to the Donald, C.
Cook Nuclear Plant Final Safety Analysis Report (FSAR).
This amendment consists of revisions to previously submitted material on the following topics:
(1)
Part length control rod removal from Unit 1, installation of permanent I
anti-rotation devices on the corresponding control rod drive mechanisms in Units 1 and 2 and editorial changes to delete references to Unit 2 within the Unit 1 description; (2)
Editorial change to the gas decay tank rupture discussion; and (3)
Editorial change to insert information on the main steam line break analysis.
A discussion of these three revisions follows.
ITEN I The information in this item is applicable to Units 1 and 2 as indicated.
In the Chapter 3 white pages, changes are made to reflect in Unit 1 the removal of the part length control rods and the installation of permanent anti-rotation de-vices on the corresponding control rod drive mechanisms.
Changes are also made REGULATORY DOCKET FILE COPY Vg04180 4!0
Mr. Harold R. Denton, Director April 4, 1979 AEP:NRC:00117 ITEM 1
CONTINUED in the Chapter 3 white pages to delete references to Unit 2 (which is addressed in the FSAR Chapter 3 yellow pages).
One change is made on Chapter 3 yellow page 3.2-57 to indicate installation of permanent anti-rotation devices in Unit 2.
The corresponding revision to reflect the absence of part length con-trol rods in Unit 2 was incorporated into FSAR chapter 3 on yellow pages as part of Amendment No. 78.
This issue was briefly mentioned for Unit 2 in Reference 1,
and the same considerations apply to Unit 1.
This change does not involve an unreviewed safety question as defined in 10 CFR 50.59(c),
and has no safety or environmental significance.
Hence, this change does not require prior NRC review or authorization, and thus the fee schedule in 10 CFR 170 is not applicable.
As you were previously informed in Reference 2, the removal of the part-length control rods and installation of anti-rotation devices in Unit 1 is planned for the refueling outage expected to begin in early April, 1979.
A change request will soon be submitted to delete Section 3/4.1.3.6, en-titled "Part Length Rod Insertion Limits",
and its Basis from the Unit 1
Appendix A Technical Specifications.
This Technical Specification requires that all part length control rods be fully withdrawn in Modes 1
and 2 and becomes moot when the part length rods are removed.
The deletions of references to Unit 2 are merely editorial changes to improve clarity and consistency because the Chapter 3 white pages are not applicable to Unit 2 and Unit 2 is covered in the Chapter 3 yellow pages.
This part of the Chapter 3 revision does not require NRC review and therefore the fee schedule in 10 CFR 170 is not applicable.
ITEM 2 The information in this item is applicable to both Units 1
and 2.
In the Section 14.2.3 white pages, a change is made in the quoted value of the calculated radioactivity release due to gas decay tank rupture to make this value consistent with the corresponding calculated whole body dose value quoted later on the same page.
This revision was inadvertently overlooked when the latter value was changed in FSAR Amendment No. 21.
This change does not re-quire NRC review.
Therefore, the fee schedule in 10 CFR 170 is not applicable.
Mr. Harold R. Denton, Director April 4, 1979 AEP:NRC:00117 ITEM 3 The information in this item is applicable to Unit 2 only.
In Appendix 9 on yellow pages, replacement is made of the response to guestion 022.9 on main steam line break analysis.
The original response to guestion 022.9 was a commitment to supply certain information concerning the main steamline break analysis.
This information was previously sub-mitted for NRC review by means of Reference 3.
The correction of an obvious typographical error in Table 022.9-4 (in the first column Tma should be 328.0, not 238.0) does not change the conclusions.
This re-vision merely incorporates formally previously submitted information into the Unit 2 FSAR and does not require NRC review.
Therefore, the fee schedule in 10 CFR '170 is not applicable.
Very truly yours, Sworn and subscribed to before me this Q~ day of April > 1979 New York County, New York ohn E. Dolan ice President Notary Public NOTARY
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REFERENCES 1)
Supplement 7 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S:. Nuclear Regulatory Commission, in the matter of Donald C.
Cook Nuclear Plant, Unit No. 2.
2)
Letter dated December 20, 1978 from the Indiana
& Michigan Power Company (Mr. John Tillinghast) to the NRC office of Nuclear Reactor Regulation (Mr. H.
R. Denton).
3)
Letter dated September 22, 1978 from the Indiana
& Michigan Power Company (Mr. John Tillinghast) to the NRC Office of Nuclear Reactor Regulation (Mr. H.
R. Denton).
Mr. Harold R. Denton, Director 0
April 4, 1979 AEP:NRC:00117 cc:
R.
C. Callen P.
W. Steketee G. Charnoff R. J. Vollen R. Walsh D. V. Shaller
-Bridgman R.
W. Jurgensen