ML20091M617
| ML20091M617 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/07/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8406110366 | |
| Download: ML20091M617 (5) | |
Text
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DUKE POWER GOMPANY P.O.150X 33180 CIIAHLOTTE, N.C. 28242 "t".:."2""
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June 7, 1984
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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 N3. 4 pe: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
On May 10,1984 Duke Power submitted a response to Catawba SER Open Item 17, Alarm in the Control Room for Boron Dilution Modes in All Modes of Operation.
In order to validate the analysis assumptions the following changes to the Catawba Technical Specifications are requested:
- 1. -Reactor Makeup Water Pump - Specifications 3/4.1.1.1 and 3/4.1.1.2 should be changed to limit flow to 120 gpm in Mode 5 and to 240 gpm in Modes 3 and 4.
2.
High Flux at Shutdown Alarm - Note 9 to Technical Specification Table 4.3-1 already requires verification of a setpoint of less than or equal to one half decade above background.
In order to maintain the setpoint in this range following shutdown, appropriate station procedures will be revised prior to initial criticality to require recalibration of the alarm setpoint as follows:
Following reactor shutdown -
every 30 minutes for the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;
- every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />;
- every eight hours thereafter until the countrate stabilizes.
Very truly yours, c.Z k
/
Hal B. Tucker ROS/php pag 6MPoMg
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Mr. Harold R. Denton, Director June 7, 1984 Page 2 cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector
. Catawba Nuclear Station Mr.- Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 E
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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
When in MODE 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of e.
the following factors:
1)
Reactor Coolant System boron concentration, 2)
Control rod position, 3)
Reactor Coolant System average temperature, 4)
Fuel burnup based on gross thermal energy generation, 5)
Xenon concentration, and 6)
Samarium concentration.
4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1% Ak/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.1.le., above.
The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after cach fuel loading.
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1 CATAWBA - UNIT 1 3/4 1-2 i
REACTIVITY CONTROL SYSTEMS g
SHUTDOWN MARGIN - T,yg 5,200*F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGI!! shall be greater than or equal to 1% ok/k.
APPLICABILITY: MODE 5.
ACTION:
' With the SHUTD'0WN MARGIN less than 1% Ak/k, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMEhfS 4.1.1 kl e SHUTDOWN MARGIN shall be determined to be grt::ater than or equal to 1%
k:
a.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an i
, _.able control rod (s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and
.b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:
1)
Reactor Coolant System boron concentration, 2)
Control rod position, 3)
Reactor Coolant System average temperature, 4)
Fuel burnup based on gross thermal energy generation, 5)
Xenon concentration, and 4
6)
Samarium' concentration.
4.1.1. 2. 2.
on. Re,ck.e tLkeup(J.6r pamp sbWl be clenionsfraled inoper ble a4 lea.sf once p er. 31 Jays bg vecifying f4a/ 7'/w a
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CATAWBA - UNIT 1 3/4 1-3
s 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that:
(1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughou'. core life as a function of fuel depletion, boron concentration, and T The most restrictive condition avg.
occurs at E01., with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled Reactor Coolant System cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% ak/k is required to control the reactivity transient.
Accrirdingly, the SHUTDOWN MARGIN requirement is based upon this limiting conoition and is consistent with FSAR safety analysis assumptions. With T less than 200 F, the reactivity transients resulting from a postulated ste$r$9 line break cooldown are minimal and a 1% ak/k SHUTDOWN MARGIN provides adequate protection.
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3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MOC used in the FSAR analyses to nominal operating conditions.
These corrections 6 %c.
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CATAWBA - UNIT 1 B 3/4 1-1
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