ML20090A194
| ML20090A194 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/06/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.11, TASK-2.K.3.12, TASK-2.K.3.17, TASK-2.K.3.25, TASK-2.K.3.30, TASK-TM NUDOCS 8407110284 | |
| Download: ML20090A194 (2) | |
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DUKE POWER GOMPANY P.O. ISOX 33180 CIIAHLOTTE N.G. 28242 HALB. TUCKER TELEPHONE w.e,arernswr (704) 373-4531 m m..
m Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station, Unit 1 Docket No. 50-413
Dear Mr. Denton:
7 As a result of discussions with NRC Staff reviewers, we are submitting a revision to Table 1.9-1 (page 16), TMI Concern II.K.3.17, Report on Outages of Emergency Core-Cooling Systems. This change is a restatement of a commitment which is discussed in the SER, Section 13.5.2.
The attached page will appear in Revision 12 to the FSAR.
Very truly yours,
& lb.
Hal B. Tucker LTP/php Attachment cc: Mr. James P. O'Reilly Palmetto Alliance Regional Administrator 21351 Devine Street U. S. Nuclear Regulatory Commission Columbia, South Carolina 29205 Region II 101 Marietta Street, NW, Suite 2900 Mr. Jesse L. Riley Atlanta, Georgia 30323 Carolina Environmental Study Group 854 Henley Place NRC Resident Inspector Charlotte, North Carolina 28207 Catawba Nuclear Station Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 pp}fdf8okhi A
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.y Table 1.9-1 (Page 16)
Response to TMI Concerns
.II.K.3.10 PROPOSED ANTICIPATORY TRIP MODIFICATION See Section 7.2.
II.K.3.11 JUSTIFICATION FOR USE OF CERTAIN PORV'S See II.D.1 II.K.3.12 CONFIRM EXISTENCE OF ANTICIPATORY REACTOR TRIP UPON TUR8INE TRIP See Section 7.2 II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICENSEE REPORT l
AND PROPOSED TECHNICAL SPECIFICATION CHANGES Q
Duke will develop and implement a plan to compilate ECC systems or components
- 440.T.6 involved in outages.
The plan will require a periodic report which contains (1) ECC system or components involved, (2) outage dates and duration of outages, (3) cause of the outage, and-(4) corrective action taken. Test and maintenance outages will be included.
The report will be reviewed and changes g
440*T*9 pr p sed to improve the availability of ECC equipment, if needed.
This plan will be developed prior to fuel load.
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~II.K.3.25 EFFECTS OF LOSS OF ALTERNATING-CURRENT POWER ON PUMP SEALS At the Catawba Nuclear Station the reactor coolant pump seal water is supplied by-the charging pumps and cooled by component cooling water.
Nuclear service water in turn cools the component cooling water.
In the event of a loss of off-site power, the component cooling water pumps, the nuclear service water pumps, and the charging pumps are all supplied with emergency power from the emergency j
diesel generators.
II.K.3.30 REVISED SMALL-BREAK LOSS-OF-COOLANT-ACCIDENT METHODS TO SHOW COMPLIANCE WITH 10 CFR PART 50, APPENDIX K i
This item requires that the analysis methods used by NSSS vendors and/or l
fuel suppliers for small-break LOCA analysis for compliance with Appendix K
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to 10 CFR Part 50 be revised, documented, and submitted for NRC approval.
i Westinghouse feels very strongly and Duke agrees that the small-break LOCA analysis model currently approved by the NRC for use on Catawba is conserva-tive and in conformance with Appendix K to'10 CFR Part 50.
However, (as documented in Letter 0G-60, dated June 15, 1981, R. W. Jurgensen (Chairman, Westinghouse Owners Group) to P. S. Check (NRC), Westinghouse believes that improvement in the realism of small-break calculations is'a worthwhile effort and has committed to revise its small-break LOCA analysis model to i
address.
hRC concerns (e.g., NUREG-0611, NUREG-0623, etc.).
This revised I.
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Rev. 12
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