ML20095G983

Proposed Tech Specs,Allowing Operation W/Increased Core Flows

ML20095G983
Person / Time
Site:	Peach Bottom
Issue date:	08/24/1984
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20095G971	List: ML20095G967 ML20095G973 ML20095G983
References
NUDOCS 8408280278
Download: ML20095G983 (7)

Text

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Unit 3 PBAPS LIST OF_ FIGURES Figure Title 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 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 MCPR Operating Limit vs. Tau, LTA 142 3.5.K.2 MCPR Operating Limit vs. Tau, PTA & P8X8R 142a Fuel 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, 142e Unit 3, 8X8 PTA Fuel 3.5.1.G 7eleted 3.5.1.H MAPLHGR vs. Planar Average Exposure, 142g Unit 3, P8X8R Fuel (P8DRB284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, 142h Unit 3, P8X8R Fuel (P8DRB299) 3.5.1.J MAPLHGR vs. Planar Average Exposure, 1421 Unit 3, P8X8R Fuel (Generic) 3.5.1.K MAPLHGR vs. Planar Average Exposure, 142j Unit 3, 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 164a or 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 l

3.6.F.3, 3.6.F.4, 3.6.F.5 and 3.6.F.6 s

6.2-1 Managem2nt Organization Chart 244 6.2-2 Organization for conduct of Plant Operation 245

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PBAPS UNIT 3 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING J

l 2.1.A (Cont'd)

In the event of the operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows.

S less than or equal to (0.66 W + 54% -0.66 delta W)

(

FRP

)

MFLPD

where, FRP = fraction of rated thermal power (3293 MWt)

MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8x8 fuel.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value

[

is less than the design value of 1.0, in which case the actual operating value will be used.

2. APRM--When the. reactor mode switch is in the.STARTUP position, the APRM scram shall be set at less than or equal to 15 percent of rated power.

3. IRM--The IRM scram shall be set at less than or equal to l

120/125 of full scale....

PBAPS Unit 3 LIMITING TONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

1. Following one pump operation,

l. Establish a baseline APRM the discharge valve of the low and' LPRM neutron flux noise speed pump may not be opened value for the regions for unless the speed of the faster which monitoring is required pump is less than 50%

. (Specification 3.6.F.6) within of its rated speed.

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 base-lining has previously been performed in the region since the last refueling outage.

2. The requirements applicable to single loop operation as identified in sections 1.1.A, 2.1.A, 2.1.B, 3.5.I & 3.5.K shall be in effect within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following th: removal of one recirculation loop from service, or the unit placed in the Hot Shutdown conditions.

3. Whenever the reactor is in the startup or run modes, two reactor coolant system recirculation loops shall be in operation,except as specified in 3.6.F.4, 3.6.F.5, and 3.6.F.6 below, with:

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.

4.

One reactor coolant system recirculation loop may be inoperable, provided the Thermal Power is less than or equal to the limit specified in Figure 3.6.5.

5.

With no reactor coolant system recirculation loops in l

operation, immediately initiate action to reduce Thermal Power to less than or equal to the limit specified in Figure 3.6.5 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 />.

-R(lg9-

PBAPS Unit 3 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS 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 INTENTIONALLY LEFT BLANK than the limit specified in Figure 3.6.5, or with one reactor coolant system recirculation loop not in operation and the Thermal Power greater than the limit specified in Figure 3.6.5

a. Determine the APRM and LPRM noise levels:

1) At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

2) Within 30 minutes after the completion of a Thermal Power increase of at least 5% of Rated Thermal Power.

b. With the APRM or LPRM neutron flux noise levels greater than three times their established baseline noise levels, immediately initiate corrective action to restore the noise levels 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 Thermal Power to less than or equal to the limit specified in Figure 3.6.5.

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.

-149a-t l

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t PBAPS Unit 3 LLIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.G STRUCTURAL 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~1ife 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.

-149b-

1 Unit 3 PBAPS 3.6.F & 4.6.F BASES Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is below 50%

of its rated speed provides assurance when going from one to two pump operation that excessive vibration of the jet pump risers will not occur.

Operation with one recirculation loop in service is permitted.

In such instances, the designated adjustments for APRM rod block and scram setpoints, RBM setpoint, MCPR fuel cladding integrity safety limit, MCPR operating limits, and MAPLHGR limits are required.

Thermal power and core flow limitations are prescribed in accordance with General Electric Service Information Letter No. 380, rev. 1, "BWR Core Thermal Hydraulic Stability," dated 2/10/84.

Neutron flux noise limits are established to ensure early detection of limit cycle neutron flux oscillations.

BWR cores typically operate with neutron flux noise caused by random boiling and flow noise.

Typical neutron flux noise levels of 1 to 12% of rated power (peak-to peak) have been reported for the range of low to high recirculation loop flow during both single and dual recirculation loop operation.

Neutron flux noise levels significantly larger than these values are considered in the thermal /mechancial fuel design and are found to be of negligible consequence, and in compliance with stability licensing criteria.

In addition, stability tests at operating BWR's have demonstrated that when stability related neutron flux limit cycle oscillations occur they result in peak-to peak neutron flux limit cycles 5 to 10 times the typical values.

Therefore, actions taken to reduce neutron flux noise levels exceeding three (3) times the typical value are sufficient to ensure early detection of limit cycle neutron flux oscillations.

Data to establish baseline APRM and LPRM neutron flux noise values is obtained at or below the power specified i

in Figure 3.6.5 for use in monitoring noise levels during operation in the region for which monitoring is required.

- 160 -

FIGURE 3 6.5 THERMAL POWER LIMITS OF SPECIFICATIONS 3.6.F.3, 3.6.F.4, 3.6.F.5 and 3.6.F.6

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