ML20065N604

Rev 1 to Millstone Unit 2 Cycle 11 Core Operating Limits Rept.

ML20065N604
Person / Time
Site:	Millstone
Issue date:	11/30/1990
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20065N594	List: ML20065N590 ML20065N604
References
NUDOCS 9012120210
Download: ML20065N604 (8)

Text

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Docket No. 50-336 Millstone Unit No. 2 Cycle 11 Core Operating Limits Report Revision 1 l

November,1990 9,gg21ggj(( $O0b g6 P

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1. CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The Technical Specifications affected by this report are listed below:

Section Snecification 2.1 3/4.1.1.1 SHUTDOWN MARGIN - T v, > 200*F 2.2 3/4.1.1.2 SHUTDOWN MARGIN - T v, s 200*F 2.3 3/4.1.1.4 Moderator Temperature Coefficient 2.4 3/4.1.3.6 Regulating CEA Insertion Limits 2.5 3/4.2.1 Linear Heat Rate 2.6 3/4.2.3 Total Integrau _ Radial Feaking Factor - F[

2.7 3/4.2.6 DNB Margin Terms appearing in capitalized type are DEFMED TERMS as defined in Section 1.0 of the Technical Specifications.

2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC. approved methodoligies specified in Technical Specification 6.9.1.7, 2.1 SHUTDOWN MARGIN - T.,, > 200*F (Specification 3/4.1.1.1)

The SHUTDOWN 14ARGIN shall be 2 3.6% AK/K 2.2 SHUTDOWN MARGIN - Tov, s 200*F (Specification 3/4.1.1.2)

The SHUTDOWN MARGIN shall be 2 2.0% AK/K 2.3 Moderator Ten.perature Coefficient (Specification 3/4.1.1.4)

The moderator tem.pern:ure coefficient shall be:

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

b. Less positive than 0.4 x 10-4 AK/K/*F whenever THERMAL POWER is > 70% of RATED THERMAL POWER,

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

November.1990

" i-i Page 2  ;

'2,4 : - Regulating CEA Insertion Limits (Specification 3/4.1.3.6) l The regulating CEA groups shall be limited to the withdrawal sequence and i 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 to:

a. s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, j

b. - s 5 Effective Full Power Days per 30 Effective Full Power Day interval, and c

c. 's 14 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:' 1

a. .15.1-kw/ft when the reactor coolant flow rate measured per Specification:4.2.6.12 340,000 gpm. i

b. 14.5 kw/ft when the reactor coolant flow rate measured per  !

Specification 4,2.6.1 2 325,000 gpm and < 340,000 gpm.

- During operation with the linear heat rate being. monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall remain' within the limits of Figure ?2.5-1. 9 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 t_o the liniit when the .following factors are appropriately _ included sin the setting of the alarms:

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

12. -A measurement-calculational uncertainty factor of 1.07,

3. - An engineering uncertainty factor of 1.03, 4

• A linear heat rate uncertainty factor of 1,01 due to axial fuel dendfication and thermal expansion, and r

5. A THERMAL POWER measurement uncertainty factor of 1.02. ,

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

November,1990

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

The calculated value of Ff, defired as Ff = Fr(1+T q), shall be limited to:

a. 0.90 < PF s 1.00 Ff s 1.790 - (0.15 x PF)

b. 0.80 < PF s 0.90 Pf s 1.925 - (0.30 x PF)

c. 0.70 < PP s 0.80 Pf s 2.205 - (0.65 x PF)

d. PF s 0.70 Ff s 1.750 where, PF = THERMAL POWER divided by RATED THERMAL POWER 2.7 DNF. Margin (Specification 3/4.2.6)

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

Parameter Limits Four Reactor Coolant Pumos Onerations

a. Cold Leg Tempereture s 549'F

b. Pressurizer Pressure 2 2225 psia *

c. Reactor Coolant Flow Rate 2 325,000 ppm

d. AXIAL SHAPE INDEX FIGURE 2.7-1

• Limit not applicable during either a THERMAL POWER ramp increase in excess of Src of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

l November.1990

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-0.6 -0,4 -0.2 0 0.2 0.4 0.6 Axial Shape Index FIGURE 2.7-1 AXIAL SHAPE INDEX Operating Limits with Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 November,1990