ML20211H078
| ML20211H078 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/27/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20211H082 | List: |
| References | |
| NUDOCS 8611040433 | |
| Download: ML20211H078 (4) | |
Text
DUKE POWER GOMPANY P.O. box 33189 CHARLOTTE, N.C. 28242 TELEPHO!tE HAL B. TUCKER (704) 373-4531 voom Peseanery NUCLEAS PSDDUCTION d
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October 27, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4 Re: Catawba Nuclear Station, Units 1 and 2 Dockat Nos. 50-413 and 50-414 Technical Specification Amendment for the Auxiliary Feedwater Pump Turbine
Dear Mr. Denton:
This letter contains proposed amendments to the Technical Specifications for Facility Operating License Nos. NPF-35 and NPF-52 for Catawba Units 1 and 2.
The attachments contain the proposed changes and a discussion of the justification and safety analysis. The analyses are included pursuant to 10 CFR 50.91 and it has been concluded that the proposed amendment does not involve significant hazards considerations.
l This request involves changing the allowable rpm for the Auxiliary Feedwater pump turbine.
f This request is applicable to the Catawba Units 1 and 2 Technical Specifications, accordingly, pursuant to 10 CFR 170.21 a check for $150.00 is enclosed.
Pursuant to 10 CFR 50.91 (b)(1) the appropriate South Carolina State Official is l
being provided a copy of this amendment request.
Very truly yours, 07 l
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Hal B. Tucker dl 4gl[9 f0 0k RWO/41/slb 0\\
,0 Attachment i
l 8611040433 641027 PDR ADOCK 05000413 P
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Mr. Harald.R. Denten, Dirscter October 27, 1986 Page Two Dr.'J. N'lson Grace, Regional Administrator xc:
e U. S. Nuclear Regulatory Commission Region II-101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &
' Environmental Control 2600 Bull Street Columbia, South Carolina 29201 INPO Records Center.
Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 NRC Resident Inspector Catawba Nuclear Station
Mr. Harcld R. D:nton, Directcr Ocfober 27, 1986 Page Four HAL B. TUCKER,.being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Consnission this revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License Nos. NPF-35 and NPF-52; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
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Hal B. Tucker, Vice President Subscribed and sworn to before me this 27th day of.0ctober, 1986.
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.s JUSTIFICATION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION The proposed change to Technical Specification 4.7.1.2.la.2) would allow the rpm of the Auxiliary Feedwater (CA) pump turbine to be adjusted up to 3800 rpm.
Although the pump has satisfied the current requirement while being operated turbine at 3600 rps, the change from 3600 rpm up to 3800 rps will improve the margin available to satisfy the requirements.
Discussions with the manufacturer indicate that the pump and turbine can be safely operated at speeds up to 3800 rpe with no adverse effects.
The manufacturer has stated that the design and operating analyses for the pump turbine will not be affected if the pump turbine is operated at or below 3800 rpm.
With an allowed increase from 3600 rps to up to 3800 rpm, the CA turbine-driven pump will have added margin to better meet the Technical Specification required head and flow. There will be no adverse effects on the CA pump or pump turbine since the pump and pump turbine were designed and analyzed by the manufacturer for operation up to and including 3800 rpm.
10 CFR 92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:
(1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated;'or (3) Involve a significant reduction in a margin of safety.
The proposed change does not involve any increase in the probability or consequences of an accident previously evaluated. This change would allow the adjustments which will allow the CA turbine-driven pump to better fulfill its intended function during an accident and thus would potentially decrease the consequences of an accident.
The proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.since the changes introduce no new mode of plant operatio~n (only slightly higher operating speed) and no physical modifications (other.than adjustment of the CA pump turbine governor) are required to be performed to the plant.' Operation of the CA turbine-driven pump at the increased speed-has been evaluated and found acceptable by the manufacturer.
l The proposed changes do not involve a significant reduction in a margin of safety.
In actuality, the proposed amendment would allow adjustment of the CA pump turbine governor such that the pump will be able to better perform its safety function.
Therefore, the overall margin of safety will be increased with the issuance of this proposed change.
Based upon the above discussion, Duke Power concludes that the proposed amendment does not involve significant hazards considerations.
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