ML20098F109

Proposed Tech Specs Re Recirculation Pumps,Structural Integrity & Thermal Power & Core Flow Limits

ML20098F109
Person / Time
Site:	Peach Bottom
Issue date:	09/21/1984
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20098F104	List: ML20098F103 ML20098F109
References
NUDOCS 8410020328
Download: ML20098F109 (6)

Text

_

PBAPS UNIT 3 LIST OF FIGURES Figure Title Page L

1.1-1 APRM Flow. Bias Scram Relationship To Normal 16 Operating Conditions 4.1.1 Instrument Test Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test 98 Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution P

-3.4.2 Required. Temperature vs. Concentration for 123 Standby Liquid Control System Solution 3.5.K.1 MCPR Operating Limit vs. Tau, LTA 142

.3.5.K.2 MCPR Operating Limit vs. Tau, PTA & P8X8R Fuel 142a 3.5.1.A DELETED 3.5.1.B DELETED 3.5.1.C~ DELETED ~

3.5.1.D DELETED 3.5.1.E Kf Factor vs. Core Flow 142d 3.5.1.F.

MAPLHGR vs. Planar Average Exposure, Unit 3 142e 8X8 PTA Fuel

. 3.5.1.G DELETED 3.5.1.H MAPLHGR vs. Planar Average Exposure, Unit 3 142g P8X8R Fuel (P8DRB284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, Unit 3 142h P8X8R LTA (P8DRB299) 3;5.1.J MAPLHGR vs. Planar Average Exposure, Unit 3 142i P8X8R Fuel (Generic) 3.5.1.K MAPLEGR vs. Planar Average Exposure, Unit 3 142j P8X8Q LTA _ (P8DQB326) 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2

-Minimum Temperature for Mechanical Heatup or 164a Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b (Criticality) 3.6.4 Transition Temperature Shift vs. Fluence 164c 3.6.5 Thermal Power Limits of Specifications 164d 3.6.F.3, 3.6.F.4, 3.6.F.5, 3.6.F.6 and 3.6.F.7 3.8.1 Site Boundary and Effluent Release Points 216e 6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245

-iv-8410020328 840927 PDR ADOCK 05000278 P

PDR

PBAPS Unit 3 LIMITING CONDITION FOR O'PERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

1. Following one pump operation,

l. Establish baseline APRM and LPRM the discharge valve of the low neutron flux noise values for speed pump may not be opened each operating mode at or below unless the speed of the faster the thermal power specified in pump is less than 50%

Figure 3.6.5 (Line A) for of its rated speed.

the regions for which monitor-ing is required (Specification 3.6.F.6, Regions 1,2 or 4) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless baselining has previously been performed since the last refueling outage.

2. The requirements applicable to

2. Establish a baseline core plate single loop operation as differential pressure noise identified in sections 1.1.A, value at or below the thermal 2.1.A, 2.1.B, 3.5.I & 3.5.K power specified in Figure 3.6.5 shall be in effect within 24 (Line A) and at a total core hours following the removal of flow less than or one recirculation loop from equal to 45% of rated core service, or the unit placed in flow for the regions for the Hot Shutdown conditions.

which monitoring is required (Specification 3.6.F.7, Regions

3. Eheaever the reactor is in the 2 or 3) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> startup or run modes, two of entering the region for reactor coolant system which monitoring is required recirculation loops shall be in unless baselining has operation,except as previously been performed specified in 3.6.F.4, 3.6.F.5, since the last refueling 3.6.F.6, and 3.6.F.7 below, with:

outage, a.

Total core flow greater than or equal to 45% of rated core flow, or; b.

Thermal Power less than or equal to the limit specified in Figure 3.6.5 (Line A).

4. With only one reactor coolant system recirculation loop operating, immediately initiate action to reduce thermal power and be below the limit specified in Figure 3.6.5 (Line A) or increase core flow to greater than or equal to 45% of rated core flow.

-149-

y.

PBAPS

?

Unit 3 LIMITING CONDITION'FOR dPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

5. With no reactor coolant system recirculation loops in operation, immediately initiate action to reduce Thermal Power to less than or equal to the limit specified in Figure 3.6.5 (Line A) and if a recirculation loop cannot be returned to service initiate measures to place the unit in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

6. With two reactor coolant system recirculation loops in operation and total core flow less than 45% of rated core flow and Thermal Power greater than the limit specified in Figure 3.6.5 (Line A) (Region 1), or with only one reactor coolant system recirculation loop operating and the Thermal Power greater than the limit specified in Figure 3.6.5 (Line A) (Regions 1 or 2) or total core flow less than 45% of rated core flow with Thermal Power greater than 35% of Rated Thermal Power (Regions 1 or 4):

a.

Determine the APRM and LPRM l

noise levels:

1) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after entering the region for which monitoring is required and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the completion of a Thermal Power increase of at least 5% of Rated Thermal Power.

l

b. With the APRM or LPRM

- neutron flux noise levels greater than 5% and three times their established baseline noise levels, immediately initiate corrective action to restore i

the noise levels to within i

l

-149a-l

PBAPS Unit 3

_LIMITI!!G CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS the required limits within 2 I

hours, or reduce thermal power at a rate which would l

bring the reactor to the hot shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, unless the noise levels are restored within the required limits during this period.

Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

7.

With one reactor coolant system recirculation loop in operation and total core flow greater than 45%

of rated core flow (Regions 2 or 3):

a. Determine the core plate differential pressure noise level:

1) At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2) Within one hour after completion of a core flow increase of at least 5% of rated core flow,

b. With the core plate dif ferential pressure noise level greater than-1 psi and 1.5 times the established baseline noise level, immediately initiate corrective action to restore the noise level to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce core flow to less than 45% of rated core flow.

-149b-

.t PBAPS Unit 3

• ~

LIMITING CONDITION FOR OPERATION

. SURVEILLANCE REQUIREMENTS 3.6.G STRUCTUEAL INTEGRITY 4.6.G STRUCTURAL INTEGRITY The' structural integrity of The non-destructive inspections of the primary system boundary listed in Table 4.6.1 shall be shall be maintained at the performed as specified. The the level required by the results obtained from compliance original acceptance standards with the specficiation will throughout the life of the be evaluated after 5 years station.

The reactor shall and the conclusions of this be maintained in a Cold evaluation will be reviewed with Shutdown condition until the NRC.

each indication of a defect has been investigated and evaluated.

-149c-

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. = I, Ll FIGURE 3.6.5

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'lllERMAL IMER AND CORE FIN IJMITS OF SPECIFICATIONS 3.6.F.3, 3.6.F.4, 3.6.F.5, 3.6.F.6 and 3.6.F.7 I!

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70 i

mm mm iem n.n...n.. n... ~.. - -

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. Stability Monitoring (APRN, LPRM & Core

! 'i Plate AP) Required for Sigole Recirc Imop

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- REION 2 -

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' Stability Monitoring (APRM & LPRM) i "y l,;l, i

60 Required for Dual Recirc loop 1,

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Operation (Single loop Operation

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,o Not Permitted)

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Stability Monitoring (Core Plate AP) 30 i1 l

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- REION 3 -

i Stability Monitoring Not Required T

20

- REION 5 -

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30 40

.)O 60 10 CORE FIN (% RATED) i i

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