ML20203B124
| ML20203B124 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/09/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20203B128 | List: |
| References | |
| NUDOCS 8604180022 | |
| Download: ML20203B124 (5) | |
Text
e DUKE POWER GOMPANY P.O. nox 33180 CILARLOTTE. N.C. 28242 liAL B. TUCKER TEIJEPHONE s nos Fareenen (704) 373-4538 htTAEAm PRODt'CTIO8f April 9, 1986 o
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
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Re: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Amendments for Radiation Monitor EMF-39 and the Auxiliary Building Filtered Exhaust System
Dear Mr. Denton:
t This letter contains proposed amendments to the Technical Specifications for Facility Operating License Nos. NPF-35 and NPF-48 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 amendments do not involve significant hazards considerations.
These requests involve changing the setpoint for radiation monitor EMF-39 and increasing the allowed outage time for the Auxiliary Building Filtered Exhaast System from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 7 days.
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 Of ficial is being provided a copy of this amendment request.
Very truly yours, g /b-n Hal B. Tucker RWO/jgu yf g
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o Mr. Harold R. Denton, Director April 9, 1986 Page 2 xc:
Dr. J. Nelson Grace, Regional Administrator 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 Mr. P.H. Skinner NRC Resident Inspector Catawba Nuclear Station i
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1 Mr. Harold R. Denton, Director April 9, 1986 Page 4 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 Commission this revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License Nos. NPF-35 and NPF-48; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
M Hal B. Tucker, Vice President Subscribed and sworn to before me this 9th day of April,1986.
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9 ATTACHMENT 1 RADIATION MONITOR EMF-39 SETPOINT
. JUSTIFICATION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION The proposed changes to the Technical Specification Table 3.3-6, Table Notations, would allow the trip setpoint for radiation monitor EKF-39 to be set and adjusted based upon activity inside containment.
The current Alarm / Trip setpoint in Table 3.3-6 Item 1.a on EMF-39 cannot be maintained at the 2 mR/hr limit during non-release periods without the EMF staying in alarm. This renders the monitor useless not only for part 1.a but also 1.b and Technical Specification 3.4.6.1. concerning Reactor Coolant System Leakage.
The function of EMF-39 should be to indicate rapid or unexpected changes to effluent release activity or changes in atmosphere due to Reactor Coolant leakage. By using three times the process activity, slight or slow changes as well as sudden changes will be observed without the moaitor staying in constant alarm.
10 CFR 50.92 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 1
[
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.
i The proposed change does not involve any increase in the probability or consequences of an accident previously evaluated. This change would allow the setpoint for ENF-39 to be adjusted according to the conditions within I
containment. The adjustments will allow the radiation monitor to fulfill its intended function during an accident and thus would potentially t
decrease the consequences of an accident.
The proposed amendment would not create the possibility of a new or i
different kind of accident from any accident previously evaluated since the changes introduce no new mode of plant operation and no physical modifications are required to be performed to the plant.
The proposed changes do not involve a significant reduction in a margin of i
safety. In actuality, the proposed amendment would allow adjustment of a radiation monitor setpoint such that the monitor will be able to better i
j perform its safety function. Therefore, the overall margin of safety will be increased with the issuance of this proposed change.
l Based upon the above discussion, Duke Power concludes that the proposed l
amendment does not involve significant hazards considerations.
i l
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