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Amend 107 to License DPR-56,changing Tech Specs Reoperating Limit Min Critical Power Ratio & Adding Restrictions to Operation in Regions of Potential thermal-hydraulic Instability
	ML20101F840
Person / Time
Site:	Peach Bottom
Issue date:	12/03/1984
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co
Shared Package
ML20101F843	List: ML20101F840; ML20101F851;
References
	DPR-56-A-107 NUDOCS 8412270333
	Download: ML20101F840 (14)
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uy'o, UNITED STATES v

"t NUCLEAR REGULATORY COMMISSION h

WASHING TON, D. C. 20555 k.....

PHILADELPHIA ELECTRIC COMPANY l

PUBLIC SERVICE ELECTRIC AhD GA5 COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. DPR-56 1.

The Nuclear Reculatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated May 30, 1984, as supplemented by letters dated August 24, 1984, and September 27, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

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. g Technical Specifications The' Technical Specifications contained in Appendices A and B, as revised through Amendment No. 107, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR R GUL ORY.p0MMISSION F

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h F. Stolz, Chief p ating Reactors Bra

4 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 3,1984 2

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ATTA' HMENT TO LICENSE AMEN 0 MENT N0.107 C

FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-278 Replace the.following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the are'a of change.

Remove Insert iv iv 10 10 133d 133d 133e 133e 142a 142a 149 149 149a 149b 149c 160 160 164d 1

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PBAPS UNIT 3 LIST OF FIGURES Figure Title Page 1.1-1 APRM Flow Bias Scrum 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 j

Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution 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 l

3.5.1.A DELETED l

3.5.1.B DELETED 3.5.1.C DELETED 1

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 1429 P8X8R Fuel (P8DRB 284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, Unit 3 142h P8X8R Fuel (P8DRB299) 3.5.1.J MAPLHGR vs. Planar Average Exposure, Unit 3 1421 P8X8R Fuel (Generic) 3.5.1.K MAPLHGR vs. Planar Average Exposure, Unit 3 142j P8X80 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 follcWing 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 Limi,ts of Specifications 164d 3.6.F.3, 3.6.F.4, 3.6.F.5, 3.6.F.6 and 3.6.F.7 6.2-1

!!anagement Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245 Am:ndment flo. JA, AJ, M, $$, $2, 77,

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SAFETY: LIMIT LIMITING SAFETY SYSTEM SETTING 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 i

(0.66 W + 544 -0.66 delta W)

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MFLPD l

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

MFLPD = maximum fraction _of limiting power density where the limiting t

power density is 13.4 KW/ft for.all 8x8 fuel.

4 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 j

rated power.

3. IRM--The IRM scram shall be i

set at less than or equal to 120/125 of full scale.

Am:ndment No. 74, 3), A7, J2, F, 7),107.

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PBAPS Unit 3 Table 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure **

BOC to 2000 MWD /t 2000 MWD /t bef ore EOC Before EOC To EOC PTA & P8X8R 1.26 1.28 LTA 1.26 1.28 If requirement 4.5.K.2.a is met.

j These values shall be increased by 0.01 for single loop cperation.

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PBAPS Unit 3 Table 3.5.K.3 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure **

BOC to 2000 MWD /t 2000 MWD /t bef ore EOC Before EOC To EOC 1

PTA & P8X8R 1.33 1.40 LTA.

1.33 1.40 1

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

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

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LIMITING CONDITION FOR OPERATION 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 i

single loop operation as differential pressure noise l

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 i

hours following the removal of flow less than or i

one recirculation loop from equal to 45% of rated core service, or the unit placed in flow for the regions for I

the Hot Shutdown conditions.

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

3. Whenever the reactor is in the 2 or 3) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

Am:ndment No. M. JT,107

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@ nit 3 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

5. With no-reactor coolant system recirculation loops in operation, immediately initiate 4

action to reduce Thermal Power j

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 noise levels:

1) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after entering the region for which monitoring is

.equired and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 5% and three times their established baselir.e noise levels, immediately initiate corrective action to restore the noise levels to within Amendment No.107

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS l

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

g 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%

1 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 differential 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce core flow to less than 45% of rated core flow.

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Amendment No.107

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LIMITING 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 performed as specified. The the level required by the results obtained from compliance original acceptance standards with the specification 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.

1 Amendment No.107

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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 / mechanical 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 valuet is obtained at or below the power specified l

in Figure 3.6.5 for use in monitoring noise levels during l

operation in the region for which monitoring is required.

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