ML20210G213

Amend 192 to License DPR-40,revising TS Sections 2.2 & 2.10. 2 to Relocate 3 cycle-specific Parameters to Core Operating Limits Repts

ML20210G213
Person / Time
Site:	Fort Calhoun
Issue date:	07/27/1999
From:	Stephen Dembek NRC (Affiliation Not Assigned)
To:
Shared Package
ML20210G193	List: ML20210G185 ML20210G213 ML20210G218
References
NUDOCS 9908030035
Download: ML20210G213 (8)

Text

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, g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001 OMAHA DUBLIC POWER DISTRICT DOCKET NO. 50-285 i FORT CALHOUN STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.192 License No. DPR-40

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated January 29,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; l

R. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulativns of the Commission; There is reasonable assurance: (i) that the activities authorized by this  !

C.

amendment can be conducted with )ut endangering the health and safety of the public, and (ii) that such activities wi! be conducted in compliance with the Com>< /ibn's r(7 elations; D.- The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and

!. E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:

B. Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 192 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Y

, Step en Dembek, Chief, Section 2 Project Directorate IV & Decommissioning I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i 1

Date of issuance: July 27, 1999 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 192 j

FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285

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Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain verticallines i

indicating the areas of change.

REMOVE INSERT f

viii vis 2-19d 2-19d j

2-19e 2-19e Figure 2-11 ~ l 2-50 2-50 2-50f 2-50f l

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TECHNICAL SPFCEFICATIONS - FIGtRES l'

TABLE OF CONTENTS PAGE WHICH FIGURE DESCRIPTION FIGURE FOLLOWS 1-1 TMLP Safety Limits 4 Pump Operations ...............................1-3 2-1 A RCS Pressure-Temperature Limits for Heatup . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 2-1B RCS Pressure-Temperature Limits for Cooldown . . . . .....................2-6 2-3 Predicted Radiation Induced NDTT Shift . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 l

2-12 Boric Acid Solubility in Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2-19h 2-10 Spent Fuel Pool Region 2 Storage Criteria ........... . ............. . 2-39e 2-8 Flux Peaking Augmentation Factors .... ............................ 2-53 1

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viii Amendment No. 110,120.131.141.101.17^, ; 72,100. 192

1 2.0 - LIMITING CONDITIONS FOR OPERATION 2.2 Chemical and Volume Control System (Continued) 2.2.7 Borated Water Source - Shutdown Anolicability Applies to the operational status of borated water sources in MODES 4 and 5 when fuel is in the reactcr. 4 Obiective i

To assure operability of equipment required to add negative reactivity.

Specification ,

As a minimum, one of the following borated water sources shall be OPERABLE:

a. _ Boric acid storage tank CH-11 A with the contents of the tank in accordance with the COLR for a SIRW tank boron concentration at REFUELING BORON CONCENTRATION, and with the ambient temperature of the boric acid solution greater than or equal to the solubility temperature of Figure 2-12.

b. _ Boric acid storage tank CH-11B with the contents of the tank in accordance with the COLR

- for a SIRW tank boron concentration at REFUELING BORON CONCENTRATION, and with the ambient temperature of the boric acid solution greater than or equal to the mlubility temperature of Figure 2-12.

c. Both boric acid storage tanks CH-11A and CH-11B with the combined contents of both tanks in accordance with the COLR for a SIRW tank boron concentration at REFUELING l BORON CONCENTRATION, and with the ambient temperature of the boric acid solution l greater than or equal to the solubility temperature of Figure 2-12.  !

d. The SIRW tank with:

1. A minimum useable borated water volume of 10,000 gallons,

2. A minimum boron concentration of REFUELING BORON CONCENTRATION, and

3. A minimum solution temperature of 50*F.

Required Actions (1)_ With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

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2-19d Amendment No. +72,192

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2.0 LIMITING CONDITIONS FOR OPERATION

2.2 Chemical and Volume Control System (Continued) 2.2.8 Borated Water Sources - Operating Applicabihty Applies to the operational status of borated water sources whenever the reactor coolant temperature (T ) is greater than or equal to 210*F.

. Obiective I

To assure operability of equipment required to add negative reactivity.

Specification .

Both of the following borated water sources shall be OPERABLE:

a. At least one boric acid storage tank (CH-11 A or CH-11B) with the contents of the tank in accordance with the COLR, or both boric acid storage tanks (CH-11 A and CH-11B) with the combined contents of both tanks in accordance with the COLR, and with the ambient temperature of the boric acid solution greater than or equal to the solubility temperature of Figure 2-12.

b. The SIRW tank with:

1. A minimum useable borated water volume of 25,000 gallons, .

2. A minimum boron concentration of REFUELING BORON CONCENTRATION, and

3. A minimum solution temperature of 50*F.

- Required Actions (1) With the above required boric acid storage tank (<,) inoperable, restore the tank (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

(2) With the SIRW tank inoperable, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least suberitical and < 300"F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

t (3) With the required actions of(1) not met, or with no OPERABLE borated water source, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least subcritical and < 300*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

2-19e Amendment No. W2,192

. 2.0 LIMITING CONDITIONS FOR OPERATION 2.10 Reactor Core (Continued)

. 2.10.2 Reactivity Control Systems and Core Physics Parameters I.imits Applicability Applies to operation of control element assemblies and monitoring of selected core parameters whenever the reactor is in cold or hot shutdown, hot standby, or power operation condituns.

Obiective To ensure (1) adequate shutdown margin following a reactor trip, (2) the MTC is within the limits of the safety analysis, and (3) control element assembly operation is within the limits of the setpoint and safety analysis. .

Specification (1) Shutdown 'Marain With T > 210 F Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be greater than or equal to the value specified in the COLR. With the shutdown margin less than the value specified in the COLR, initiate and continue boration until the required shutdown margin is achieved.

(2) Shuhlown Marnin With T <210 F Whenever the reactor is in cold shutdown conditions, the shutdown margin shall be13.0% Ak/k. With the shutdown margin <3.0% Ak/k, initiate and continue boration until the required shutdown margin is achieved.

(3) Moderator Temnerature Coefficient  !

The moderator temperature coefficient (MTC) shall be:

a. Lesspositivethan +0.2x104Ap/ Fincludinguncertainties forpowerlevels at or above 80% of rated power.-

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b. Less positivethan +0.5x10 Ap/ Fincludinguncertainties forpowerlevels below 80% of rated power.

c. More positive than the value specified in the COLR including uncertainties l at rated power.

With the moderator temperature coefficient confirmed outside any one of above limits, change reactivity control parameters to bring the extrapolated MTC value ,

within the above limits within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2-50 Amendment No. 8,32,43,47,62,70,77,143,192 1

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. ' 2.0 LIMITING CONDITIONS FOR OPERATION 2.10 Reactor Com (Continued) i

. 2.10.2 Reactivity Control Systems and Core Physics Parameters Limits (Continued) {

2. The position of each trippable CEA required shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and

3. Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50%

withdrawn position within 7 days prior to reducing the Shutdown Margin to less than the limits of Specification 2.10.2(1).

(ii). If the shutdown margin specified in part (i) above is not available l

immediately, initiate and continue boration until the requirernents of i 2.10.2(1) are met.

(iii) The shutdown margin specified in part (i) above shall be verified every 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift.

c. Moderator Temperature Coefficient (i) The moderator temperature coefficient (MTC) requirements of 2.10.2(3) may be suspended during physics tests at less than 10-'%

of rated power. j (ii) If power exceeds 10-'% of rated power, either:

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1. Reduce power to less than 10-3% of rated power within 15 minutes, or

2. Be in hot shutdown in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

B.aEiS Shutdown Marain A sufficient shutdown margin ensures that (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will te maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

Shutdown margin requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,,,. The most restrictive condition occurs at EOL, with T,,, at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum shutdown margin as specified in the COLR is initially adequate to control the l reactivity transient. Accordingly, 2-50f Amendment No. 32,43,47,70,140,192