ML17261A416

Amend 22 to License DPR-18,revising Requirements of Tech Specs Dealing W/Control Rod Indications,Resulting from Replacement of Analog Rod Position Indication Sys W/ Westinghouse Microprocessor Rod Position Indication Sys

ML17261A416
Person / Time
Site:	Ginna
Issue date:	02/10/1987
From:	Diianni D Office of Nuclear Reactor Regulation
To:
Shared Package
ML17261A417	List: ML17261A416 ML17261A418
References
NUDOCS 8702190375
Download: ML17261A416 (21)

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qo Wp*y0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POMER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No.

DPR-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated October 24, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

The issuance of this amendment will not be inimical to the common

'efense 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 Commission'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-18 is hereby amended to read as follows:

870Z190375 870210 PDR ADOCK 05000244-P PDR

~

~ (2)

Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.22

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

Attachment:

Changes to the Technical Specifications FOR THE NUCLEAR REG LATORY COMMISSION Dominic C.

Di Ianni, Project Manager Project Directorate Pl Division of PWR Licensing-A Date of Issuance:

February 10, 1987

ATTACHMENT TO LICENSE AMENDMENT N0.22 FACILITY OPERATING LICENSE NO.

DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE 3.5-7 3.10-2 3.10-7 3.10-8 3.10-9 3.10-10 3.10-13

3. 10-14

3. 10-18

3. 10-19 0

4. 1-5

4. 1-6

4. 1-8 INSERT

3. 5-7 3.10-2 3.10-7 3.10-8 3.10-9 3.10-10 3.10-13 3.10-14 3.10-14a 3.10-18 3.10-19 3.10-19a 4.1-5 4.1-6 4.1-8 4.1-9

TABLE 3.5-1 (Continued)

Page 2 of 3 NO.

FUNCTIONAL UNIT 11.

Turbine Trip 3

2 Maintain 50/ of Rated Power OPERATOR ACTION

.NO.

OF MIN.

MIN.

PERMISSIBLE IF CONDITIONS OF NO.

OF CHANNELS OPERABLE DEGREE OF BYPASS COLUMN 3 OR 5 CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS CANNOT BE MET 12.

Steam Flow Feedwater 2/loop 1/loop 1/loop 1/loop Flow Mismatch With Lo Steam Generator Level Maintain hot shutdown 13.

Lo Lo Steam Generator Water Level 3/loop 2/loop 2/loop 1/loop Maintain hot shutdown Undervoltage 4 KV Bus 2/bus 1/bus 1/bus n

Maintain hot shutdown Underfrequency 4 KV Bus 16.

quadrant Power Tilt Monitor (Upper 6 Lower Ex-Core Neutron Detectors) 2/bus 1/bus 1/bus (both busses) 1 or Log individual upper 6 lower ion chamber currents once/hr 6 after a load change of 10$ or after 48 steps of control rod motion n

n Maintain hot shutdown Maintain hot shutdown

3.10.1.2 When the reactor is critical except for physics tests 3.10.1.3 and control rod exercisep, the shutdown control rods shall be fully withdrawn (indicated position).

When the reactor is critical, except for physics tests and control rod exercises, each group of control rods shall be inserted no further than the limits shown by the lines on Figure 3.10-1 and moved sequentially with a 100

(+5) step (demand position) overlap between successive banks.

3.10.1.4 During control rod exercises indicated in Table 4.1-2, the insertion limits need not be observed but the Figure 3.10-2 must be observed.

3.10.1.5 The part length control rods will not be inserted except for physics tests or for axial offset calibration performed at 75% power or less.

3.10.1.6 During measurement of control rod worth and shutdown margin, the shutdown margin requirement, Specification 3.10.1.1, need not be observed provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion and all part length control rods are fully withdrawn.

Each full length control rod not fully inserted, that is, the rods available for trip insertion, shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position (indicated) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the shutdown margin to less than the limits of Specification 3.10.1.1.

The position of each full length rod not fully inserted, that is, available for trip insertion, shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

3. 10-2 Amendment No 22

0 I,

t

3.10.2.12 When the reactor is critical and thermal power is less than or equal to 90% of rated

power, an alarm is provided to indicate when the axial flux difference has been outside the target band for more than one hour (cumulative) out of any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

In.

addition, when thermal power is greater than 90% of rated

power, an alarm's provided to indicate when the axial flux difference is outside the target band.

If either alarm is out of service, the flux difference shall be logged hourly for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the 3.10.3 alarm is out of service and half-hourly thereafter.

Control Rod Dro Time 3.10.3.1 While critical, the individual full 'length (shutdown and control) rod drop time from the fully withdrawn position (indicated) shall be less than or equal to 1.8 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

a.

T greater than or equal to 540'F, and avg

b..All reactor coolant pumps operating.

3.10.3.2 With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to criticality.

3. 10. 4 Control Rod Grou Hei ht 3.10.4.1 While critical, and except for physics testing, all full length (shutdown and control) rods shall be operable and positioned within

+ 12 steps (indicated position) of their group step counter demand position.

3.10-7 Amendment No.

22

3.10.4.2 With any full length rod inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untripable, determine that the shutdown margin requirement of Specification 3.10.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in hot 3.10.4.3 shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With one full length rod inoperable due to causes other than addressed by 3.10.4.2,

above, or misaligned from its group step counter demand position by more than

+ 12 steps (indicated position), operation may continue provided that within one hour either:

3.10.4.3.1 The rod is restored to operable status within the above alignment requirements, or 3.10.4.3.2 The rod is declared inoperable and the shutdown margin requirement of Specification 3.10.1.1 is satisfied.

Operations may then continue provided either:

. a.

The remainder of the rods in the group with the inoperable rod are aligned to the same indicated position as the inoperable rod within one hour, while maintaining the limit of Specification 3.10.1.3; or b.

The power level is reduced to less than or equal to 75% of rated power within the next one hour, and the high neutron flux trip setpoint is reduced to less than or equal to 85% rated power within the next four hours (total of six hours) and the following evaluations are performed:

(i)

The shutdown margin requirement of Specification 3.10.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3 ~ 10-8 Amendment No.

22

(ii) A power distribUtion map is obtained from the movable incore detectors and F

(Z) and F <H N

are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

(iii) A reevaluation of each accident analysis of Table 3.10-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents. remain valid for the duration of operation under these conditions.

c. If power has been restricted in accordance with (b) above, then following completion of the evaluation identified in (b), the power level and high neutron flux trip.setpoint may be readjusted based on the results of the evaluation provided the shutdown margin requirement of Specification 3.10.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.10.4.4 With two or more full length rods inoperable or misaligned from the group step counter demand position by more than 2 12 steps (indicated position),

be in hot shutdown 3.10.5 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Control Rod Position Indication S stems 3.10.5.1 While critical, the rod position indication system and the step counters shall be operable and capable of determining the control rod positions within i 12 steps.

3.10-9 Amendment No.

22

With a maximum of one rod position indication per bank inoperable either:

a.

Determine the position of the non-indicating rod(s) indirectly by the movable incore detectors 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 immediately after any motion of the non-indicating rod which exceeds 24 steps (demand position) in one direction since the last determination of the rod's position, or b.

Reduce the power to less than 50% of rated power within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

With a maximum of one step counter per bank inoperable either:

a.

Verify that position indication'or each rod of the affected bank is operable and that the rods of the bank are at the same indicated position at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or b.

Reduce the power to less than 50% of rated power within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Basis The reactivity control concept is that reactivity changes accompanying changes in reactor power are compensated by control rod motion.

Reactivity changes associated with xenon,

samarium, fuel depletion, and large changes in reactor coolant temperature (operating temperature to cold shutdown) are compensated by changes in the soluble boron concentration.

During power operation.

the shutdown groups are fully withdrawn 3.10-10 Amendment-No.

22

conditions are as follows':

1.

Control rods in a single bank move together with no individual rod insertion differing by more than 25 steps from the bank demand position.

2.

Control rod banks are sequenced with overlapping banks as described in Specification 3.10.

3.

The full length control bank insertion limits are not violated.

4.

Axial power distribution limits which are given in terms of flux difference limits and control bank insertion limits are observed.

Flux difference is q

q as defined in Specification 2.3.1.2d.

The permitted relaxation in F >H with reduced power allows radial power shape changes with rod insertion to the insertion limits. It has been determined that provided the above conditions 1 through 4 are observed, these hot channel factors limits are met.

In Specification 3.10, F

is arbitrarily limited for P

< 0.5 (except for lower power physics tests).

The limits on axial power distribution referred to above are designed to minimize the effects of xenon redistribution on the axial power distribution during load-follow maneuvers.

Basically, control of flux difference is required to limit the difference between the current value of Flux Difference (AI) and a reference value which corresponds to the full power equilibrium 3.10-13 Amendment No.

22

value of Axial Offset: (Axial Offset = BI/fractional power).

The reference value of flux difference varies with power level and burnup but expressed as axial offset it varies primarily with burnup.

The technical specifications on power distribution assure that the F

upper bound envelope of 2.32 times Figure 3.10-3 is not exceeded and xenon distributions are not developed which, at a later time, could cause greater local power peaking even though the flux difference is then within the limits.

The target (or reference) value of flux difference is determined as follows.

At any time that equilibrium xenon conditions have been established, the indicated flux d-'fference is noted with part length rods withdrawn from the core and with control Bank D more than 190 steps (indicated position) withdrawn.

This value, divided by the fraction of full power at which the core was operating is the full power value of the target flux difference.

Values for all other core power levels are obtained by multiplying the full power value by the fractional power.

Since the indicated equilibrium value was

noted, no allowances for excore detector error are necessary and indicated deviation of 2 5 percent, hI is permitted from the indicated reference value.

During per'iods where extensive load following is 3.10-14 Amendment No.

22

required, it may be impossible to establish the required core conditions for measuring the target flux difference every month.

For this reason, two methods are

3.10-14a Amendment No.

22

feet out of alignment with its bank) does not result in exceeding core. safety limits in steady state operation at rated power and is short with respect to probability of an independent accident.

If instead of determining the hot channel factors, the operator decides to reduce power, the specified 75% power maintains the design margin to core safety limits for up to 1.12 power tilt, using the 2 to 1 ratio.

Reducing the overpower trip set point ensures that the protection system basis is maintained for sustained plant operation.

A tilt ratio of 1.12 or more is indicative of a serious performance anomaly and a plant shutdown is prudent.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses.

Measurement.

with T greater than or avg equal to 540'F and with both reactor'oolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

The various control rod banks (shutdown banks, control banks A,B,C, and D) are each to be moved as a bank; that is, with all rods in the bank within one step (5/8 inch) of the bank position.

Positron indication is provided by two methods:

a digital count of actuation pulses which shows the

3. 10-18 Amenament Ho.

22

demand position of. the banks and a microprocessor rod position indication (MRPI) system which indicates the actual rod position.

The digital counters are known as the step counters.

Operability of the control rod position indication is required to determine control rod positions and thereby ensure compliance. with the control rod alignment and insertion limits.

The 12 step permissible demand to indicated misalignment and the 0 step rod to rod indicated misalignment ensures that the 25 step misalignment assumed in the safety analysis is met.

The MRPI system displays the position of all rods on a CRT.

A failure of the CRT would result in loss of position indication of the rods even though the MRPI system

'I is still operable.

Since the MRPI system also transmits rod position information to the Plant Process Computer System

{PPCS), the PPCS can be used for rod position indication until the CRT is made operable.

The action statements which permit limited varia-tions from the basic reguirements are accompanied by additional restrictions which ensure that the original design criteria are met.

Misalignment of a rod requires measurement of peaking factors or a 3.10-19 Amendment No.

22

restriction in power; either of these restrictions provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

References:

(1)

Updated Final Safety Analysis Report, (UFSAR)

Section 4.2.

3.10-19a Amendment No.

22

TABLE 4.1-1 NININUN FREQUENCIES FOR CHECKSI CALIBRATIONS AND TEST OF INSTRUNENT CHANNELS Channel Check 1.

Nuclear Power Range SN*(3)

Cal ibra te D(1)

Q*(3)

Test B/W(2)(4)

P(2)(5)

Remarks

1) Heat balance calcula tion**

2) Signal to WT; bistable action (permissiveI rod stops trips)

3) Upper and lower chambers for axial offset**

4) High setpoint

(<109% ot rated pter) 5)

Low setpoint

(<25% of rated power) 2.

Nuclear Intermediate S(l)

Range N.A.

P(2)

1) Once/shift when in service

2) Log level; bistable action (permissive>

rod stop< trip) 4.

Reactor Coolant Temperature S

3.

Nuclear Source Range S(l)

N.A.

P(2)

N(l)

(2)

1) Once/shift when in service

2) Bistable action (alarmI trip)

1) Overtemperature-Delta T

2) Overpower Delta T

5.

Reactor Coolant Flow S

6.

Pressurizer Water S

Level 7.

Pressurizer Pressure S

R Be 4 Kv Voltage Frequency N.A.

Reactor Protection circuits only 9.

Rod Position Indication S(1,2)

N.A.

1) With step counters 2)

Log rod position indications each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when rod deviation monitor is out of service By means of the movable in-core aetector system.

• • Not required during hotI cold, or refueling shutdown but as soon as possible after return to power.

TABLE 4.1-1 (Continued)

Channel 10.

Rod Position Bank Counters Check S(1,2)

Calibrate N.A.

Test N.A Remarks

1) With rod position indication

2) Log rod position indications each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when rod deviation monitor is out of service ll. Steam Generator Level S

12. Charging Flow N.A N A.

13. Residual Heat Removal N.A.

Pump Flow N.A.

14. Boric Acid Tank Level D

N.A.

Bubbler tube rodded weekly

15. Refueling Water Storage Tank Level 16.

Volume Control Tank Level N.A N.A.

NBA.

N.A.

17. Reactor Containment Pressure D

M(l)

1) Isolation Valve signal

18. Radiation Monitoring System D

Area Monitors Rl to R9<

System Monitor R17

19. Boric Acid Control N.A N A.

20. Containment Drain

B Sump Level R.

21. Valve Temperature e

Interlocks 22.

Pump-Valve Interlock O

23. Turbine Trip Set-Point N.A.

N.A.

N.A.

N.A.

N A ~

N.A N.A.

M(l)

1) Block Trip

24. Accumulator Level and Pressure N.A.

TABLE 4.1-2 MINIMUM FREQUENCIES FOR EQUIPMENT ANB SAMPLING TESTS 1.

Reactor Coolant Chemistry Samples Test Chloride and Fluoride Oxygen Frequency 3 times/week and at least every third day 5 times/week and at least every second day except when below 250 F FSAR Section Reference 2.

Reactor Coolant Boron Boron concentration Weekly 3.

Refueling Water Storage Tank Water Sample Boron concentration Weekly 4.

Boric Acid Tank 5.

Control Rods 6.a Full Length Control Rod Boron concentration Rod drop times of all full length rods Move any rod not fully inserted a sufficient number of steps in any one direction to cause a change of position as indicated by the rod position indication system Twice/week After vessel head removal and at least once per 18 months (1)

Monthly 6.b Full Length Control Rod Move each rod through its full length to verify that the rod position indication system transistions occur Each Refueling Shutdown 7.

Pressurizer Safety Valves 8.

Main Steam Safety Valves Set point Set point Each Refueling Shutdown Each Refueling Shutdown 10 9.

Containment Isolation Trip 10.

Refueling System Interlocks Functioning Functioning Each Refueling Shutdown Prior to Refueling Opera tions 9.4.5 4.1-8 Amendment No.

22

ll.

Service Water System 12.

Fire Protection Pump and Power Supply Test Functioning Functioning

~Fre uencg Each Refueling Shutdown Monthly FSAR Section Reference 9.5.5 9.5.5 13.

Spray Additive Tank NaOH Concent.

Monthly 14.

Accumulator 15.

Primary System Leakage Boron Concentration Evaluate Bi-Monthly Daily 17.

Spent Fuel Pit 18.

Secondary Coolant Samples Boron Concentration Gross Activity 16.

Diesel Fuel Supply Fuel Inventory Daily Monthly 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (2)(3) 8.2.3 9.5.5 19.

Circulating Water Flood Protection Equipment Calibra te Each Refueling Shutdown Notes:

(1)

Also required for specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods.

(2)

(3)

Not required during a cold or refueling shutdown.

An isotopic analysis for I-131 equivalent activity is required at least. monthly whenever the gross activity determination indicates iodine concentration greater than 10% of the allowable limit but only once per 6 months whenever the gross activity determination indicates iodine concentration below 10% of the allowable limit.

4.1-9 Amendment No.

22