ML18059A374

Proposed Tech Specs Table 3.23-2 Re Radial Peaking Factor Limits for Cycle 11

ML18059A374
Person / Time
Site:	Palisades
Issue date:	09/03/1993
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
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ML18059A371	List: ML18059A369 ML18059A372 ML18059A374 ML18059A375
References
NUDOCS 9309140081
Download: ML18059A374 (14)

Text

ATTACHMENT I Consumers Power Company Pali sades Pl ant Docket 50-255 PROPOSED TECHNICAL SPECIFICATIONS PAGES

--- r--.1, 9309140081 930903 u*

PDR ADOCK 05000255

\\

P PDR September 3, 1993 4 Pages

2.0 BASIS - Safety Limits and Limiting Safety System Settings 2.3 Basis - Limiting Safety System Settings (continued)

5.

Low Steam Generator Water Level - The low steam generator water level reactor trip protects against the loss of feed-water flow accidents and assures that the design pressure of the primary coolant system will not be exceeded.

The specified set point assures that there will be sufficient water inventory in the steam generator at the time of trip to allow a safe and orderly plant shutdown and to prevent steam generator dryout assuming minimum auxiliary feedwater capacity.<6>

The setting listed in Table 2.3.1 assures that the heat transfer surface (tubes) is covered with water when the reactor is critical.

6.

Low Steam Generator Pressure - A reactor trip on low steam generator secondary pressu.re is provided to protect against an excessive rate of heat extraction from the steam generators and subsequent cooldown of the primary coolant.

The setting of 500 psia is sufficiently below the rated load operating point of 739 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessively high steam flow.

This setting was used in the accident analysis. <5>

7. Containment High Pressure - A reactor trip on containment high pressure is provided to assure that the reactor is shutdown before the initiation of the safety injection system and containment spray.<7>

References (1)

EMF-92-178, Revision 1, Table 15.0.7-1 (2)

Updated FSAR, Section 7.2.3.3.

(3)

EMF-92-178, Revision 1, Section 15.0.7-1 (4)

XN-NF-86-9l(P)

(5)

ANF-90-078, Section 15.1.5 (6)

ANF-87-150(NP), Volume 2, Section 15.2.7 (7)

Updated FSAR, Section 7.2.3.9.

(8)

ANF-90-078, Section 15.2.1 Amendment No 3-i-, s.2-, HS, -l-3-7, -!W,.§.6.

B 2-5

3.1 PRIMARY COOLANT SYSTEM (Cont'd)

Basis (Cont'd) measurement; +/-0.06 for ASI measurement; +/-50 psi for pressurizer pressure;

+/-7°F for inlet temperature; and 3% measurement and 3% bypass for core flow.

In addition, transient biases were included in the derivation of the following equation for limiting reactor inlet temperature:

Tinlet ~ 542.99 +.0580(P-2060) + O.OOOOl(P-2060)**2 + 1.125(W-138) -

.0205(W-138)**2 The limits of validity of this equation are:

1800 < pressure < 2200 psia 100.0-x 106 ~Vessel Flow~ 150 x 106 lb/h ASI as shown in Figure 3.0 With measured primary coolant system flow rates> 150 M lbm/hr, limiting the maximum allowed inlet temperature to the T~nlet LCO at 150 M lbm/hr increases the margin to DNB for h1gner PCS flow rates<4>.

The Axial Shape Index alarm channel is being used to monitor the ASI to ensure that the assumed axial power profiles used in the development of the inlet temperature LCO bound measured axial power profiles. The signal representing core power (Q) is the auctioneered higher of the neutron flux power and the Delta-T power. The measured ASI calculated from the excore detector signals and adjusted for shape annealing (Y1) and the core power constitute an ordered pair (Q,Y 1).

An alarm signal is activated before the ordered pair exceed the boundaries specified in Figure 3.0.

The requirement that the steam generator temperature be ~ the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This requirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg temperature is< 430°F.

However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System is isolated from the PCS, forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.

References (1)

Updated FSAR, Section 14.3.2.

(2)

Updated FSAR, Section 4.3.7.

(3)

Deleted (4)

EMF-92-178, Revision 1, Section 15.0.7.1 (5)

ANF-90-078 (6)

Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3 Amendment No. 3-l-, &l-, -H-7, -HS, Hl, H4' -l-3-7' +/-43' -l-5-6

3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY Applicability Applies to the moderator temperature coefficient of reactivity for the core.

Ob.iective To specify a limit for the positive moderator coefficient.

Specifications The moderator temperature coefficient (MTC) shall be less positive than +0.5 x 10-4 Ap/°F at s 2% of rated power.

The limitations on moderator temperature coefficient (MTC) are provi~ed to ensure that the assumptions used in the safety analysisc 1>

remain valid.

Reference (1)

EMF-92-178, Revision 1, Section 15.0.5 3-67 Amendment No. -l-l-8, 7,.f-43., ~

(next page is 3-69)

II Peaking Factor Assembly FA r Peak Rod FT r Peak Rod TABLE 3.23-1 LINEAR HEAT RATE LIMIT TABLE 3.23-2 RADIAL PEAKING FACTOR LIMITS, FL Reload L & M Reload N 1.57 1.66 1.92 1.92 TABLE 3.23-3

15. 28 kW/ft Reload 0

1. 76 2.04 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS II LHR/Peaking Factor Measurement Measurement Measurement Uncerta i nty<a>

Uncerta i nty

Uncerta i nty<c>

{a}

{b}

{c}

Parameter LHR 0.0623 0.0664 0.0795 FA r 0.0401 0.0490 0.0695 FT r

0.0455 0.0526 0.0722 Measurement uncertainty for reload cores using all fresh incore detectors.

Measurement uncertainty for reload cores using a mixture of fresh and once-burned incore detectors.

Measurement uncertainty when quadrant power tilt, as determined using incore measurements and an incore analysis computer program'6', exceeds 2.8% but is less than or equal to 5%.

3-107 Amendment No. 68, -l-f-8,.f-43., -+/-44, ~

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED TO SHOW THE PROPOSED CHANGES September 3, 1993 5 Pages

-~* -;-.*-~.:*- := *--:.~*~

e 2.0 BASIS - Safety Limits*and Limiting Safety System Settings 2.3 Basis - Limiting Safety System Settings (continued)

5.

Low Steam Generator Water Level - The low steam generator water level reactor trip protects against the loss of feed-water flow accidents and assures that the design pressure of the primary coolant system will not be exceeded.

The specified set point assures that there will be sufficient water inventory in the steam generator at the time of trip to allow a safe and orderly plant shutdown and to prevent ~team generator dryout assuming minimum auxiliary feedwater capacity. 1 The setting listed in Table 2.3.1 assures that the heat transfer surface (tubes) is covered with water when the reactor is critical.

6. Low Steam Generator Pressure - A reactor trip on low steam ~enerator secondary pressure is provided to protect against an excessive rate of heat extraction from the steam generators and subsequent cooldown of the primary coolant.

The setting of 500 psia is sufficiently below the rated load operating point of 739 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessi~rlY high steam flow.

This setting was used in the accident analysis.'

7. Containment High Pressure - A reactor trip on containment high pressure is provided to assure that the reactor is shutdown befohr the initiation of the safety injection system and containment spray. 7

• References Rl'(.;v1<;,10,,r i J (2 (LJ1-c.'t':)

1 EMF-92-178,Jlable 15.0.7-1 /

2 Updated FSAR, Section 7.2.3.3.

3 EMF-92-178, ~ection 15.0.7-1 4

XN-NF-86-9l(P~

5 ANF-90-078, Section 15.1.5 6

ANF-87-150(NP), Volume 2, Section 15.2.7 7

Updated FSAR, Section 7.2.3.9.

8 ANF-90-078, Section 15.2.1 Amendment No ~' 82-, H-8, ~, SG, -t5ir JUfte--t6-, -l-993 B 2-5

3.1 PRIMARY COOLANT SYSTEM (Cont'd)

Basis (Cont'd) measurement; +/-0.06 for ASI measurement; +/-50 psi for pressurizer pressure;

+/-7°F for inlet temperature; and 3% measurement and 3% bypass for core flow.

In addition, transient biases were included in the derivation of the following equation for limiting reactor inlet temperature:

T~~ ~ 542.99 +.0580(P-2060) + O.OOOOl(P-2060)**2 + l.125(W-138) -

.0205(W-138)**2 The limits of validity of this equation are:

1800 < pre§sure < 2200 psia 100.0-x 10

~ Vessel Flow~ 150 x 106 lb/h ASI as shown in Figure 3.0 With measured primary coolant system flow rates> 150 M lbm/hr, limiting the maximum allowed inlet temperature to the T1{11 LCO at 150 M lbm/hr increases the margin to DNB for higher PCS flow rates 141

• The Axial Shape Index alarm channel is being used to monitor the ASI to ensure that the assumed axial power profiles used in the development of the inlet temperature LCO bound measured axial power profiles.

The signal representing core power (Q) is the auctioneered higher of the neutron. flux power and the Delta-T power. The measured ASI calculated from the excore detector signals and adjusted for shape annealing {Y1) and the core power constitute an ordered pair (Q,Y1).

An alarm signal is activated before the ordered pair exceed the boundaries specified in Figure 3.0.

The requirement that the steam generator temperature be ~ the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This requirement applies only to the initiation of forced circulation (the start of the first primary coolant pump} when the PCS cold leg temperature is< 430°F.

However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System is isolated from the PCS, forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.

References 1

Updated FSAR, Section 14.3.2.

2 Updated FSAR, Section 4.3.7.

I 3

De 1 eted

{(; 1'(/u1 s.-tDr-1

)

4 EMF-92-178 ection 15.0.7.1 5

ANF-90-078.

6 Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3 Amendment No. ~' £!, H-7, H-8,

~' -l-34' -l-3-7-' Ha.' ~

June Hi, 1993-

e 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY Applicability Applies to the moderator temperature coefficient of reactivity for the COr!!.

Objective To specify a limit for the positive moderator coefficient.

Specifications The moderator temperature coefficient (MTC) shall be less positive than +0.5 x 10*4 Ap/°F at s 2% of rated power.

Bases The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the safety analysis111 remain valid.

Reference

( 1)

EMF~ 92-178 /\\Section 15. 0. 5 eJi;,.Vi'<:>IOl--/ ~

3-67 Amendment No. H-8, 3+, -143-, 'T5"6

-dune 16, 1993 (next page is 3-69)

TABLE 3.2-3-1 LINEAR HEAT RATE LIM!~-

Rods Assembly 216 TABLE 3.23-2 RADIAL PEAKING FACTOR LIMITS, FL Peaking Factor No. of Fuel Rods in Assembly 208 216 216 216 Reload M Reload N Reload 0 Assembly F~

1.48 1.57 1.66

1. 76 Peak Rod FTr

1. 92

1. 92

1. 92 2.04 TABLE 3.23-3 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS LHR/Peaking Factor Measurement Measurement Measurement Uncerta i nty'a>

Uncerta i nty'b>

Uncerta i nty'c>

(a)

(b)

(c)

Parameter LHR 0.0623 0.0664 0.0795 FA r 0.0401 0.0490 0.0695 FT r 0.0455 0.0526

0. 0722 Measurement uncertainty for reload cores using all fresh incore detectors.

Measurement uncertainty for reload cores using a mixture of fresh and once-burned incore detectors.

Measurement uncertainty when quadrant power tilt, as determined using incore measurements and an incore analysis computer program<6>, exceeds 2.8% but is less than or equal to 5%.

3-107 Amendment No 68, H-8, 43, -144, /ii dune 16, 199-3~

II Peaking Factor Assembly FA r Peak Rod FT r Peak Rod TABLE 3.23-1 LINEAR HEAT RATE LIMIT TABLE 3.23-2 RADIAL PEAKING FACTOR LIMITS, FL Reload L & M Reload N 1.57 1.66

1. 92 1.92 TABLE 3.23-3

15. 28 kW/ft Reload O

1. 76 2.04 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS II LHR/Peaking Factor Measurement Measurement Measurement Un cert a i nty<a>

Un cert a i nty

Uncerta i nty<c>

(a)

(b)

(c)

Parameter LHR 0.0623 0.0664 0.0795 FA r 0.0401 0.0490 0.0695 FT r 0.0455 0.0526

0. 0722 Measurement uncertainty for reload cores using all fresh incore detectors.

Measurement uncertainty for reload cores using a mixture of fresh and once-burned incore detectors.

Measurement uncertainty when quadrant power tilt, as determined using incore measurements and an incore analysis computer program<6>, exceeds 2.8% but is less than or equal to 5%.

3-107 Amendment No. 68, -l-f-8., -l-43-, -144, ~

ATTACHMENT 3 Consumers Power Company Pali sades Pl ant Docket 50-255 EMF-92-178, REVISION 1, PALISADES CYCLE 11:

DISPOSITION AND ANALYSIS OF STANDARD REVIEW PLAN CHAPTER 15 EVENTS.

September 3, 1993

ATTACHMENT 4 Consumers Power Company Palisades Plant Docket 50-255 SIEMENS LETTER TO R.J. GERLING DATED, SEPTEMBER 2, 1993 September 3, 1993 1 Page

200'39~d 828P8SP 902 e

SIEMENS September 2, 1993 JWH:93:07e Mr. R.J. Gerling Palisades NPS 27780 Blue Star Highway Covert, Ml 49043

Dear Mr. Gerling:

St :st 86, 2 d3S

Subject:

Technical Specification Peaking Factor Limits for Batch L Fuel fer Palisades Cycle 11

Reference:

11Pallsades Cycle 9: Analysis of Standard Review Plan Chapter 15 Events 11 ANF-90-078, Advanced Nuclear Fuels Corporation, September 9, 1990.

In response to your staff's request the appropriate peaking factor llmlts for the Reload L fuel assemblies In Cycle 11 are 1.57 for FA, and 1.92 for Fr,. The transient analyses for Cycle 9 (Reference) addresses the radial peaking llmlts for the Reload L fuel. The above limits are for Reload L fuel with 21 e rods per assembly.

If you should. ~ave any questions please contact me.

Very truly yours,

/;M~.

J. W. Hulsman Customer Service Engineer Sig cc:

T. C. Bordlne T. C. Duffy W. T. Nutt H. G. Shaw Siemens Power Corporation Nuclear Division

• Headquarters

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