ML20065K082

Rev 0 to Millstone Nuclear Power Station,Unit 2 Cycle 11 Core Operating Limits Rept

ML20065K082
Person / Time
Site:	Millstone
Issue date:	11/30/1990
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20065K078	List: ML20065K074 ML20065K082
References
NUDOCS 9011150140
Download: ML20065K082 (8)

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. Attachment 1 l Millstone Nuclear Power Station, Unit No. 2 Cycle 11  !

l Core Operating Limits Report j 1

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- CORE OPERATING LIMITS REPORT :l

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1.0 CORE OPERATING LIMITS REPORT k This- Core Operating Limits Report for Millstone 2 has ';een prepared in accordance with the requirements of Technical Specification 6.9.1.7. The [

technical specifications affected by this report are listed below: '

Section Specification

( 2.1 3/4.1.1.1 SHUTDOWN MARGIN - Tavg > 200*F L

l 2.2 3/4.1.1.2 SHUTDOWN MARGIN - T,yg 1 200'F 2.3 3/4.1.1.4 Moderator Temperature Ccefficient i 2.4- 3/4.1.3.6 Regulating CEA Insertion Limits j 2.5 3/4.2.1 Linear Hert late i 2.6- 3/4.2.3 Total Integrated Radial Peaking Factor - F T r

2.7 3/4.-2. 6 - DNB Margin 3

i Terms ap) earing in capitalized type are DEFINED TERMS as defined in Section 1.0 of tie Technical Specifications. ,

2.0 .0PERATING LIMITS l

The: cycle-specific parameter limits for the specifications listed in L Section 1.0 are presented in the following subsections. These limits have .,

been-developed- using the NRC-approved methodologies specified in Technical 2 Specification 6.9.1.7.. -l s

2.1 SHUTDOWN MARGIN - Tavg > 200'F (Specification 3/4.1.1.1) ,

The SHUT 00WN MARGIN shall be 2 3.6% AK/K 2.2; SHUTDOWN MARGIN - T,yg i 200*F-. (Specification 3/4.1.1.2)

The SHUTDOWN MARGIN shall be 12.0% AK/K '!

1 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)  ;

The moderator temperature coefficient shall: be: '

a. Less positive than 0.7 x 10 AK/K/*F whenever THERMAL POWER is 5 70% of RATED THERMAL POWER,

b. Less positive than 0.4 x 10 4- AK/K/*F whenever THERMAL POWER is

> 70% of RATED THERMAL POWER,

4. - c. Less negative than -2.8 x 10 AK/K/*F at RATED THERMAL POWER.

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m 2.4 Agulating Cre Insertion limits (Specification 3/4.1.3.6)

The regulating CEA groups shall be limited to the withdrawal sequence

, and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted tot

a. 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> per P.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> interval, b, s 5 Effective full Power Days per 30 Effective Full Power Day interval, and

c. 114 Effective full Power Days per calendar year.

2.5 Linear Heat Rate (Specification 3/4.2.1)

The Linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed:

a. 15.1 kw/f t when the reactor coolant flow ratc measured per Specification 4.2.6.1 2 340,00 gpm.

b. 14.5 kw/ft when the reactor coolant flow rate measured per i Specific:. tion 4.2.6.1 2 325,000 gpm and < 340,000 gpm.

During operation with the linear heat rate being monitored by the i Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall remain within.the limits of Figure 2.5-1.

During operation with the linear heat rate being monitored by the incore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms:

1.* Flux peaking augmentation factors as shown in Figure 2.5-2,

2. A measurement calculational uncertainty factor of 1.07,  ;

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3. An engineering uncertainty factor of 1.03, )

4.* A' linear heat rate uncertainty factor of 1.01 due to axial fuel densification and thermal expansion, and

5. A THERHAL POWER measurement uncertainty factor of 1.02.

• These factors are only appropriate to fuel batches "A" through "L".

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2.6 Total Integrated Radial Peaking Factor - F r (Specification 3/4.2.3)

T T The calculated value of Fr , defined as F r = Fr (1+Tq ), shall be limited to:

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a. 0.90 < PF 1 1.00 F r 1 (1.76 -(0.15 x PF)

b. 0.70 < PF s 0.90 F r 1 (2.1875 -(0.625 x PF)

I c._ PF s 0.70 F r 1 1.75 where, PF - THERMAL POWER divided by RATED THERMAL POWER 2.7 DNB Margin (Specification 3/4.2.6)

The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the following imits:

Limits four Reactor Coolant Parameter Pumos Operations

a. Cold Leg Temperature s 549'F

b. Pressurizer Pressure 2 2225 psia *

c. Reactor Coolant flow Rate 1 325,000 gpm

d. AXIAL SHAPE INDEX FIGURE 2.7 1

• Limit not applicable during either a THERMAL POWER ramp increase in

, excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step  ;

increase of greater than 10% of RATED THERMAL POWER.  !

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p Carolina Power & Light Company Brunswick Nuclear Project L November 12, 1990 FILE: B09 11720

. SERIAL: BSEP/.h0708 I Mr. S. D. Ebneter. Adsinistrator U. S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street NW Atlanta, CA 30323 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50 325 AND 50 324 i LICENSE NOS. DPR 71 AND DPR 62 EMERGENCY PLANNING

Dear'Mr. Ebneter:

In accordance with 10CFR50, Appendix E, Carolina Power & Light Company hereby transmits one copy 4f recent revisions to the Brunswick Steam Electric Plant emergency procedures. A list of the revisions is enclosed for your use.

If you have any questions on this subject, please contact our Regulatory Compliance staff.

Very truly yours.

Nux J. L. Ilarness, General Manager Brunswick Steam Electric Plant.

Bul/jan/90 0062.msc Enclosure cc: Resident Inspector (NRC.BSEP)

NRC Document Control Desk

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CAROLINA POWER & LICHT COMPANY-BRUNSWICK STEAN ELECTRIC PLANT UNITS 1 AND 2 e

Uu- REVISIONS TO PLANT EMERGENCY PROCEDURES p

g' SECTION NtMBER IIILE REVISION PEP.02.1 Initial Emergency Actions 028C

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Q)1 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 INITIAL EMERGENCY ACTIONS 1

PIANT EMERGENCY PROCEDURE: PEP 02.1 7, I VOLUME XIII ,

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