ML20039F845
| ML20039F845 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/04/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20039F846 | List: |
| References | |
| TAC-47493, NUDOCS 8201130459 | |
| Download: ML20039F845 (2) | |
Text
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DUKE POWER COMPANY PowEn Ut:n.ntxo 422 SocTn Curucu STREET, CHAHLoTTE, N. C. ana42 WI L LI AM O. PA R M E R, J R.
January 4, 1982 m ca-me:^au 7c*
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ST E Aho PmOD*;CTION 373-4083 Mr. Harold R. Denton, Director g
A Office of Nuclear Reactor Regulation go U. S. Nuclear Regulatory Commission
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g Washington, D. C.
20555 3,
p~ w_lVED Attention:
Ms. E. G. Adensam, Chief 2
g'
--9 Licensing Branch No. 4 E;
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.EI982 A C at 8g" O Re: McGuire Nuclear Station
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Tag Docket No. 50-369
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//
Dear Mr. Denton:
is a proposed change to the McGuire Nuclear Station Technical Specifications regarding Reactor Coolant System flow rate.
In order to permit timely and orderly escalation of Unit 1 to full power, your prompt attention to this request would be appreciated.
The proposed change has been reviewed and it has been determined that there are no adverse safety or environmental impacts associated with the proposed change.
This change is considered to be a Class III amendment pursuant to 10 CFR 170.22.
Therefore, a check in the amount of $4,000 is enclosed.
V [y truly yours,
'N' pn. _ - 4, William O. Parker, Jr.
GAC/jfw Attachment cc:
Mr. P. R. Bemis Mr. James P. O'Reilly, Regional Administrator Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
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9 '
e2o113o459 emot o4 DR ADOCK 05000369 PDR
.Mr. Harold R. Denton, Director Page 2 January 4, 1982 WILLIAM 0. PARKER, JR., 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 McGuire Nuclear Station Technical Specifications, Appendix A to License No., NPF-9; and that all statements and matters set forth therein are true and corra-t to the best f his knowledge, i
h a s. -__ &. n William O. Parker, Jr., g President Subscribed and sworn to before me this 4th day of January, 1982.
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Notary Public My Commission Expires:
September 20, 1984 i
McGuire Nuclear Station Technical Specification 3.2.3 - RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor Proposed Change: Add a note to Figure 3.2-3 to read:
" Operation above 90% RTP*may proceed for no more than 48 cumulative hours provided RCS total flow as measured by precision heat balance is greater than 395,850 gpm."
Justification and Safety Analysis
-The recently measured value for Reactor Coolant System (RCS) total flow rate is less than the minimum value specified on Figure 3.2-3 of the Technical Specifications, however, the measured value is greater than the thermal design flow (TDF) which is the flow assumed in all of the various safety analyses.
The minimum flow value in Technical Specifications includes an allowance of 3.5% for measurement accuracy.
This additional 3.5% is added to permit surveillance requirements 4.2.3.2.b. and 4.2.3.3 to be accomplished utilizing the control board indication for RCS flow rate which is derived from an elbow top in each loop.
The measured value of flow was obtained by performing a precision heat balance (calorimetric).
The uncertainty associated with this method is 1.5% as shown in A.
(In actuality the McGuire measurement was more accurate due to the special test equipment employed).
The diagram below depicts the relationship of the various flowrate values:
Tech Spec minimum value for 100% RTP TDF + 3.5%
(403,650 gpm)
Measured value (401,230 gpm) i TDF + 1.5%
(395,850 gpm) l l
l TDF (390,000 gpm) l Tech Spec minimum value for 90% RTP (383,500 gpm) l I
- Rated Thermal Power i
i l
l l
8201130462 820104 l
ADOCK 03000369 l
PDR l
-. -, - -. ~ -
The precision heat balance method provides assurance that the RCS total flow rate is'above TDF.
Operation above 90% RTP for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptab.e based on adequate margin between measured flow and TDF.
This restriction on operation above 90% will permit the installed flow instrumentation to be used for the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance requirement in 4.2.3.3 since this instrumentation has been normalized with the measured flow and instrument drift over this short period of time will be negligible.
This requested change is a temporary measure designed to permit escalation to full power to verify the full power capability of the unit and to check the performance of the Model D steam generators at full power.
Evaluations are in progress that will provide justification for a permanent change to Technical Specifications 3.2.3 to support continued full power operation.
This change has no adverse affect on safety since there is still adequate margin between TDF and actual RCS flow.
i
ATTACHMENT 1A CALORIMETRIC FLOW MEASUREMENT UNCERTAINTIES Uncertainty Instrument
% Power or Component Error
% Flow Feedwater Flow Venturi K i 0.5% K t 0.5%
Thermal Expansion coefficient Temperature i 2.0*F Material t 5.0%
1 0.06%
Density Temperature 2.0*F 0.09%
Pressure 60 psi DP Cell Calibration 0.5%
t 0.39%
DP Cell Reading Uncertainty t 1.0%
0.78%
Feedwater Enthalpy Temperature t 2.0%
0.28%
Pressure t 60 psi Steam Enthalpy Transducer Calibration i 18 psi t 0.07%
Isolator Calibration t 18 psi 0.0T%
Moisture Carryover 0.25%
0.22%
Primary Enthalpy T RTD t 0.2*F t 0.38%
R/E Converter 1 0.6 F 1.13%
Readout t 0.1 F i 0.19%
Temperature Streaming i 1.2 F t 2.27%
Pressure Effect 30 psi 0.24%
RTD 0.2*F 0.31%
T R/E Converter 0.6 F 0.94%
T Readout t 0.1*F t 0.16%
T Pressure Effect t 30 psi t 0.06%
Net Pump Heat Addition 20%
t 0.085%
Total Loop Flow Uncertainty
/Ie2 2.974%
Total Reactor Flow Uncertainty 4-loop i 1.5%
3-loop i 1.75%
2-loop 2.1%
.