ML20096H100

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Proposed Tech Specs Re Cycle 7 Operation
ML20096H100
Person / Time
Site: Peach Bottom  
Issue date: 09/07/1984
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20096H087 List:
References
NUDOCS 8409110258
Download: ML20096H100 (9)
v • d • e


Text

,

T PBAPS Unit 2

' LIST OF FIGURES Figure

~~~~~fItl ~~~~~

e Page 1.1-1 APRM Flow Bias Scram Relationship To 16 Normal Operating Conditions 4.1.1 Instrument Test-Interval Determination 55 Curves 4.2.2 Probability of System Unavailability 98 4

Vs. Test Interval 3.4.1 Required Volume and Concentration of 122 Standby _ Liquid Control System Solution 3.4.2 Required Temperature vs. Concentration 123 for Standby Liquid Control System Solution 3.5.K.1, Deleted-142 l

3.5.K.2 MCPR Operating Limit vs.~ Tau, P8X8R fuel 142a 3.5.K.3

. Deleted 142bl 3.5.1.E Kf Factor'Vs. Core Flow 142d 3.5.1.F.

Deleted 142e l 3.5.1.G Deleted.

142fl 3.5.1.H-MAPLHGR Vs. Planar Average Exposure, 1429 Unit 2, P 8X8R Fuel, Type P8DRB285, 100 mil channels 3.5.1.I MAPLHGR-vs. Planar Average Exposure, 142h

' Unit 2, P 8x8R-Fuel, Type P8DRB284 H, 80 mil & 100 mil channel & 120 mil channels r.

p~ _

-3.5.1.J.

MAPLHGR vs. Planar Average Exposure 1421 Unit 2, P8X8R and BP8X8R Fuel, Type P8DRB299 and BP8DRB299, 100 mil channels 3.5.1.K.

MAPLHGR vs. Planar Average Exposure 142j Unit 2, P8X8R Fuel (Generic)

MAPLHGR vs. Pl'nar Average Exposure 142kl

' 3. 5.1. L. :

a Unit 2, BP8X8R Fuel, Type BP8DRB299H.

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1 PBAPS l3.4~ BASES

' STANDBY LIQUID CONTROL SYSTEM A. _The conditions under which the Standby Liquid Control System

~

.must provide shutdown capability are identified via the Plant Nuclear Safety. Operational Analysis (Appendix G).

If no more than one operable control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and

the Standby Liquid Control system is not required.

Thus, the basic reactivity requirement for the core is'the primary determinant of when the liquid control system is required.

The purpose of the liquid control system is to provide the capability of bringing the reactor from full power to a cold, xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted.

To meet this objective, the liquid control system is designed to inject a quantity of boron that produces a concentration of 660 ppm of boron in the reactor core in less than 125 minutes.

The 660 ppm concentration in the reactor core will bring the reactor

'from full power to a subcritical condition, considering the hot.to cold reactivity difference, xenon poisoning, etc.

The time requirement for inserting the boron solution was selected to override the rate of reactivity insertion caused by cooldown of_the reactor following the-xenon poison peak.

The minimum limitation on the relief valve setting is intended to prevent the recycling of liquid control solution via the lifting of a relief valve at too low a pressure.

The F

upper limit on the relief valve setting provides system protection from overpressure.

L B.

Only one of the two standby liquid control pumping loops is

[

needed for operating the system.

One inoperable pumping l

circuit'does not-immediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired.

Assurance that the remaining system will perform its intended function and that the long term average availability of the system is not reduced is obtained for a one out. of two system by an allowable equipment out of service time of one third of the normal surveillance frequency.

This method determines an equipment out of

. service time of ten days.- Additional conservatism is introduced by reducing the allowable out of service time to seven days,-and by increased testing of the operable L

redundant component.

-119-

7 PBAPS Unit 2 5

L7MITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.I Average Planar LHGR 4.5.I Average Planar LHGR 7

=

W-During power operation, the APLHGR The APLHGR for cach type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily

_s exceed the limiting value shown in during reactor operation at e

the applicable figures during two 125% rated thermal power.

recirculation loop operations.

?s-During single loop operation, the APLHGR for each fuel type shall j5E not exceed the above values T-'

multiplied by the following

?-

reduction factor: 0.79 for P8X8R J75 and BP8X8R fuel.

If at any time

[--

during operation it is determined

~ r by normal surveillance that the limiting value of APLHGR is being 51 exceeded, action shall be initiated within one (1) hour to

-E restore APLHGR to within at prescribed limits.

If the APLHGR i

is not returned to within prescribed limits within five (5) hours reactor power shall be decreased at a rate which would bring the reactor to the cold t.

shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless APLHGR is returned to within limits during this period.

Surveillance and

];

corresponding action shall JE continue until reactor operation r_;

is within the prescribed limits.

Y 3.5.J Local LHGR 4.5.J Local LHGR

[

During power operation, the linear The LHGR as a function of core

&T heat generation rate (LHGR) of any height shall be checked daily

=

rod in any fuel assembly at any during reactor operation at Ir axial location sha.1 not exceed 225% rated thermal power.

design LHGR.

LHGR < LHGRd I

LHGRd = Design LHGR 13.4 kW/ft for all 8X8 fuel

  • [

4 k

-133a-

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PBAPS Unit 2 Table 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

  • MCPR Operating Iimit**

Fuel Type For Incremental Cycle _Corf.;_ Average Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC P8X8R ***

1.23 1.29 l

If requirement 4.5.K.2.a is met.

These values shall be increased by 0.01 for single loop operation.

      • Applicable to all P8X8R fuel bundles including BP8X8R l

and the P8DRB285 (Reload 5) types.

-133d-

J

'PBAPS Unit 2 Table 3.5.K.3 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE ErPOSURES*

MCPR Operating Limit **

Fuel Tyge For Incremental Cycle Core Average Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC P8X8R***

1.34 1.41 l

If surveillance requirement 4.5.K.2 is not performed.

These values shall be increased by 0.01 for single loop operation.

      • Applicable to all P8X8R fuel bundles including BP8X8R l

and the P8DRB285 (Reload 5) types.

-133e-

PEACH BOTTOM UNIT 2

FIGURE " MCPR OPERATING LIMIT vs 7 3

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PBAPS UNIT 2

'5.0 MAJOR : DESIGN FEATURES 5.1 SITE FEATURES The site is located partly in Peach Bottom Township, York County, partly in Drumore Township, Lancaster County, and partly in Fulton Township, Lancaster County, in southeastern Pennsylvania on the westerly shore of Conowingo Pond at the mouth of Rock Run Creek.

It is about 38 miles north-northeast of Baltimore, Maryland, and 63 miles west-southwest of Philadelphia, Pennsylvania. -Figures 2.2.1 through 2.2.4 of the FSAR show the site location with respect to surrounding communities.

5.2 REACTOR A.

The core shall consist of not more than 764 fuel assemblies.

B.

The reactor core shall contain 185 cruciform-shaped control rods.

5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2.2 of the FSAR.

The applicable design codes shall be as described in Table 4.2.1 of the FSAR.

5.4 CONTAINMENT A.

The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FSAR.

The applicable design codes shall be as described'in Appendix M of the FSAR.

B.

The secondary containment shall be as described in Section 5.3 of the FSAR.

C.-

Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.

-241-

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