Text

Proposed TS 3.0 & 4.0 Re SR
	ML18153D214
Person / Time
Site:	Surry
Issue date:	01/14/1993
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18153D213	List: ML18153D212; ML18153D214;
References
	NUDOCS 9301190166
	Download: ML18153D214 (24)
	v • d • e

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e ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES

(- 930i 190166 930114 PDR ADOCK 05000280 p PDR

TS 3.12-3

8. Power Distribution Limits

1. At all times except during low power physics tests, the hot channel factors defined in the basis meet the following limits:

FQ(Z) ~ 2.32/P x K(Z) for P > 0.5 FQ(Z) ~ 4.64 x K(Z) for P :s;; 0.5 F~H ~ 1.56 [1 + 0.3 (1-P)] for three loop operation

~ 1.55 [1 + 0.2 (1-P)] for two loop operation where P is the fraction of RATED POWER at which the core is operating, K(Z) is the function given in TS Figure 3.12-8, and Z is the core height location of FQ.

2. Prior to exceeding 75% power following each core loading and during each effective full power month of operation thereafter, power distribution maps using the movable detector system shall be made to confirm that the hot channel factor limits of this specification are satisfied. For the purpose of this confirmation:

. Meas

a. The measurement of total peaking factor Fa shall be increased by eight percent to account for manufacturing tolerances, measurement error and the effects of rod bow.

The measurement of enthalpy rise hot channel factor F~H shall be compared directly to the limit specified in Specification 3.12.B.1. If any measured hot channel factor exceeds its limit specified under Specification 3.12.B.1, the reactor power and high neutron flux trip setpoint shall be reduced until the limits under Specification 3.12.B.1 are met.

If the hot channel factors cannot be brought to within the limits of FQ(Z) :s;; 2.32/P x K(Z) and ~H :s;; 1.56 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the Overpower ~T and Overtemperature ~T trip setpoints shall be similarly reduced.

b. The provisions of Specification 4.0.4 are not applicable.

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TS 3.12-4

3. The reference equilibrium indicated axial flux difference (called the target flux difference) at a given power level Po is that indicated axial flux difference with the core in equilibrium xenon conditions (small or no oscillation) and the control rods more than 190 steps withdrawn. The target flux difference at any other power level P is equal to the target value at Po multiplied by the ratio P/P 0 . The target flux difference shall be measured at least once per equivalent full power quarter. The target flux difference must be updated during each effective full power month of operation either by actual measurements or by linear interpolation using the most recent value and the value predicted for the end of the cycle life. The provisions of Specification 4.0.4 are not applicable.

4. Except as modified by Specifications 3.12.B.4.a, b, c, or d below, the indicated axial flux difference shall be maintained within a+/- 5%

band about the target flux difference (defines the target band on axial flux difference).

a. At a power level greater than 90 percent of rated power, if the indicated axial flux difference deviates from its target band, within 15 minutes either restore the indicated axial flux difference to within the target band or reduce the reactor power to less than 90 percent of RATED POWER.

b. At a power level no greater than 90 percent of RATED POWER, (1) The indicated axial flux difference may deviate from its target band for a maximum of one hour (cumulative) in any 24-hour period provided the flux difference is within the limits shown on TS Figure 3.12-10.

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e e TS 4.0-1 4.0 SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance requirements provide for testing, calibrating, or inspecting those systems or components which are required to assure that operation of the units or the station will be as prescribed in the preceding sections.

4.0.2 Surveillance requirement specified time intervals may be adjusted plus or minus 25 percent to accommodate normal test sche9ules.

4.0.3 Failure to perform a surveillance requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the operability requirements for a Limiting Condition for Operation. The time limits of the Action Statement requirements are applicable at the time it is identified that a surveillance requirement has not been performed. The Action Statement requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the Action Statement requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an operational condition shall not be made unless the surveillance requirement(s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to operational conditions as required to comply with Action Statement requirements.

I .. *. A TS 4.0-2 4.0.5 Surveillance requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a. lnservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

". e e TS 4.0-3 ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing lnservice Inspection and lnservice Inspection Testing Activities and Testing Activities Monthly At least once per 31 days Quarterly or Every 3 months At least once per 92 days COLD SHUTDOWN At least once per CSD REFUELING SHUTDOWN At least once per RSD

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for pump and valve testing only. Extensions for inservice inspection of components will be to the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

TS 4.0-4 BASES 4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during all operating conditions for which the Limiting Conditions for Operation are applicable.

4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.

4.0.3 This specification establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the operability requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when surveillance requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the surveillance requirements. This specification also clarifies that the Action Statement requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the Action Statement requirements apply from the point in time it

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TS 4.0-5 is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the surveillance requirement within the allowable outage time limits of the Action Statement requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the operability requirements of a Limiting Condition for Operation. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2){i)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the Action Statement requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with Action Statement requirements, e.g., Specification 3.0.1, a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance is provided to permit a delay in implementing the Action Statement requirements. This provides an adequate time limit to complete surveillance requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with Action Statement requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This

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TS 4.0-6 provision also provides a time limit for the completion of surveillance requirements that become applicable as a consequence of condition changes imposed by Action Statement requirements and for completing surveillance requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance, the time limits of the Action Statement requirements are applicable at that time. When a surveillance is performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance and the surveillance requirements are not met, the time limits of the Action Statement requirements are applicable at the time that the surveillance is terminated.

Surveillance requirements do not have to be performed on inoperable equipment because the Action Statement requirements define the remedial measures that apply. However, the surveillance requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an operational condition specified in the applicability statement. The purpose of this specification is to ensure that system and component operability requirements or parameter limits are met before entry into a condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in operational conditions associated with plant shutdown as well as startup.

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e TS 4.0-7 Under the provisions of this specification, the applicable surveillance requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

Exceptions to Specification 4.0.4 allow performance of surveillance requirements associated with a Limiting Condition for Operation after entry into the applicable operational condition.

When a shutdown is required to comply with Action Statement requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower condition of operation.

4.0.5 This specification ensures that inservice inspection, repairs, and replacements of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a. Specific relief from portions of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activitie~ required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

TS 4.0-8 I Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provisions which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

TABLE 4.1-1

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MINIMUM FREQUENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Calibrate Remarks

1. Nuclear Power Range s D(1,5) M(2) 1) Against a heat balance standard, 0(3,5) above 15% RATED POWER R(4) 2) Signal at L\T; bistable action (permissive, rod stop, trip)

3) Upper and lower chambers for symmetric offset by means of the movable incore detector system

4) Neutron detectors may be ex-cluded from CHANNEL CALIBRATION e

5) The provisions of Specification 4.0.4 are not applicable

2. Nuclear Intermediate Range *s R(2,3) P(1) 1) Log level; bistable action (below P-1 O setpoint) (permissive, rod stop, trip)

2) Neutron detectors may be ex-cluded from CHANNEL CALIBRATION

3) The provisions of Specification 4.0.4 are not applicable

3. Nuclear Source Range *s R(2,3) P(1) 1) Bistable action (alarm, trip)

(below P-6 setpoint) 2) Neutron detectors may be excluded from CHANNEL CALIBRATION

3) The provisions of Specification 4.0.4 are not applicable

4. Reactor Coolant Temperature *s R M(1) 1) OvertemperatureL\T M(2) 2) Overpower L\T

5. Reactor Coolant Flow s R M

6. Pressurizer Water Level s R M

7. Pressurizer Pressure (High & Low) s R M

8. 4 KV Voltage and Frequency N.A. R M

9. Analog Rod Position *S(1,2) R M(3) 1) With step counters (4) 2) Each six inches of rod motion -I when data logger is out of (/)

service .i:,..

3) Rod bottom bistable action ......

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4) N.A. when reactor is in HOT, c>>

INTERMEDIATE OR COLD SHUTDOWN

TABLE 4.1-1 (Continued)

MINIMUM FREQUENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Calibrate fut Remarks

39. Steam/Feedwater Flow and Low S/G s R M(1) 1) The provisions of Specification 4.0.4 Water Level are not applicable.

40. Intake Canal Low (See Footnote 1) D R M(1), 1) Logic Test 0(2) 2) Channel Electronics Test

41. Turbine Trip and Feedwater Isolation a Steam generator water level high s R M

b. Automatic actuation logic and N.A. R M(1) 1) Automatic actuation logic only, actuation relay actuation relays tested each refueling

42. Reactor Trip System Interlocks

a. Intermediate range neutron N.A. R(1) M(2,3) 1) Neutron detectors may be excluded from flux, P-6 the calibration

b. Low reactor trips block, P-7 N.A. R(1) M(2,3) 2) With power greater than or equal to the interlock setpoint, the required test shall

c. Power range neutron flux, P-8 N.A. R(1) M(2,3) consist of verifying that the interlock is

d. Power range neutron flux, P-10 N.A. R(1) M(2,3) in the required state by observing the permissive annunciator window

e. Turbine Impulse pressure N.A. R R 3) The provisions of Specification 4.0.4 are not applicable.

Footnote 1:

~ Consists of verifying for an indicated intake canal level greater than 23'-6" that all four low level sensor channel alarms are not in an alarm state.

Caljbratjon Consists of uncovering the level sensor and measuring the time response and voltage signals for the immersed and dry conditions.

It also verifies the proper action of instrument channel from sensor to electronics to channel output relays and annunciator. Only the two available sensors on the shutdown unit would be tested.

1) The logic test verifies the three out of four logic development for each train by using the channel test switches for that train.

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2) Channel electronics test verifies that electronics module responds properly to a superimposed differential millivolt signal CX>

which is equivalent to the sensor detecting a "dry" condition. C"

TABLE 4.1-2A MINIMUM FREQUENCY FOR EQUIPMENT TESTS FSAR Section Pescrjptjon frequency Reference

1. Control Rod Assemblies Rod drop times of all Prior to reactor criticality: 7 full length rods at a. For all rods following each removal hot conditions of the reactor vessel head,

b. For specifically affected individual rods following any maintenance on or modi-fication to the control rod drive system which could affect the drop time of those specific rods, and

c. Each REFUELING SHUTDOWN.

2. Control Rod Assemblies Partial movement of Every 2 weeks 7 all rods

3. Refueling Water Chemical Functional Each REFUELING SHUTDOWN 6 Addition Tank

4. Pressurizer Safety Valves Setpoint PerTS4.0.3 4

5. Main Steam Safety Valves Setpoint PerTS4.0.3 10

6. Containment Isolation Trip *Functional Each REFUELING SHUTDOWN 5

7. Refueling System Interlocks *Functional Prior to refueling 9.12

8. Service Water System *Functional Each REFUELING SHUTDOWN 9.9

9. Fire Protection Pump and Functional Monthly 9.10 Power Supply

10. Primary System Leakage *Evaluate Daily 4

11. Diesel Fuel Supply *Fuel Inventory 5 days/week 8.5

12. Boric Acid Piping Heat *Operational Monthly 9.1 Tracing Circuits

13. Main Steam Line Trip -I Valves Functional Before each startup (TS 4. 7) 10 en (Full Closure) The provisions of Specification ~

4.0.4 are not applicable. ......

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e TS 4.2-1 4.2 AUGMENTED INSPECTIONS Applicability Applies to inservice inspections which augment those required by ASME Section XI.

Objective To provide the additional assurance necessary for the continued integrity of important components involved in safety and plant operation.

Specifications A. Inspections shall be performed as specified in T.S. Table 4.2-1.

Nondestructive examination techniques and acceptance criteria shall be in compliance with the requirements of TS 4.0.5.

B. The normal inspection interval is 1O years.

C. Detailed records of each inspection shall be maintained to allow a continuing evaluation and comparison with future inspections.

Bases The inspection program for ASME Section XI of the ASME Boiler and Pressure Vessel Code limits its inspection to ASME Code Class 1, 2, and 3 components and supports. Certain components, under Miscellaneous Inspections in this section, were added because of no corresponding code requirement. This added requirement provides the inspection necessary to insure the continued integrity of these components.

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b. The leakage rate test will be performed at a pressure of at least 39.2 psig (Pa)-

c. The measured leakage rate Lam shall not exceed 75% of the design basis accident leakage rate (La) of 0.1 weight percent per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at pressure Pa.

2. Type Band C tests will be performed at a pressure of at least 39.2 psig (Pa) in accordance with the provisions of Appendix J, Section 111.B and C.

Also, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after use of the personnel airlock, the seals will be tested at least at the peak calculated accident pressure to verify that they are properly sealed.

C. Acceptance Criteria Type A, B, and C tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J, Sections 111.A.S(b), 111.B.3, and 111.C.3 are met.

D. Retest Schedule The retest schedules for Type A, B, and C tests will be in accordance with Section 111.D of Appendix J.

E. Inspection and Reporting of Tests Inspection and reporting of tests will be in accordance with Section V of Appendix J.

F. The provisions of Specification 4.0.2 are not applicable.

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e TS 4.5-1 4.5 SPRAY SYSTEMS TESTS Applicability Applies to the testing of the Spray Systems.

Objective To verify that the Spray Systems will respond promptly and perform their design function, if required.

Specification A. Each containment spray subsystem shall be demonstrated OPERABLE:

1. By verifying, that on recirculation flow, each containment spray pump performs satisfactorily when tested in accordance with Specification 4.0.5.

2. By verifying that each motor-operated valve in the containment spray flow path performs satisfactorily when tested in accordance with Specification 4.0.5.

3. At least once per 5 years, coincident with the closest refueling outage, by performing an air or smoke flow test and verifying each spray nozzle is unobstructed.

4. Coincident with the containment spray pump test described in Specification 4.5.A.1, by verifying that no particulate material clogs the test spray nozzles in the refueling water storage tank.

B. Each recirculation spray subsystem shall be demonstrated OPERABLE:

1. By verifying each recirculation spray pump performs satisfactorily when tested in accordance with Specification 4.0.5.

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TS 4.5-2

2. By verifying that each motor-operated valve in the recirculation spray flow paths performs satisfactorily when tested in accordance with Specification 4.0.5.

3. At least once per 5 years, coincident with the closest refueling outage, by performing on air or smoke flow test and verifying each spray nozzle is unobstructed.

C. Each weight-loaded check valve in the containment spray and outside containment recirculation spray subsystems shall be demonstrated OPERABLE at least once each refueling period, by cycling the valve one complete cycle of full travel and verifying that each valve opens when the discharge line of the pump is pressurized with air and seats when a vacuum is applied.

D. A visual inspection of the containment sump and the inside containment recirculation spray pump wells and the engineered safeguards suction inlets shall be performed at least once each refueling period and/or after major maintenance activities in the containment. The inspection should verify that the containment sump and pump wells are free of debris that could degrade system operation and that the sump components (i.e., trash racks, screens) are properly installed and show no sign of structural distress or excessive corrosion.

The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank. The containment spray pump is operated and a quantity of water recirculated to the refueling water storage tank. The discharge to the tank is divided into two fractions; one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are

identical with those used in the containment spray headers. The purpose of the recirculation through the test nozzles is to assure that there are no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles.

e TS 4.7-1 4.7 MAIN STEAM LINE TRIP VALVES Applicability Applies to periodic testing of the main steam line trip valves.

Objective To verify the ability of the main steam line trip valves to close upon signal.

Specification A. Tests and Frequencies

1. Each main steam line trip valve shall be tested for full closure before each .startup, unless a satisfactory test has been conducted within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The provisions of Specification 4.0.4 are not applicable.

B. Acceptance Criteria

1. A full closure test of a main steam line trip valve shall be considered satisfactory if the following criteria are met:

a. T1 less than or equal to 4.0 seconds and

b. T2 less than or equal to 5.0 seconds where

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TS 4.8-1 4.8 AUXILIARY FEEDWATER SYSTEM Applicability Applies to periodic testing of the Auxiliary Feedwater System.

Objective To verify the ability of the auxiliary steam generator feedwater pumps and their ability to respond properly when required.

Specification A. Tests and Frequencies

1. Each main steam line trip valve shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability.

2. The turbine driven auxiliary steam generator feedwater pump shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability. The provisions of Specification 4.0.4 are not applicable.

3. The auxiliary steam generator feedwater pump discharge valves shall be exercised on a monthly basis.

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TS 4.8-2 4a. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to temperature and pressure exceeding 350°F and 450 psig respectively, the motor driven auxiliary feedwater pumps shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators.

4b. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after achieving reactor criticality, the steam turbine driven auxiliary feedwater pump shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators. The provisions of Specification 4.0.4 are not applicable.

5. During periods of extended reactor shutdown, the testing requirements of Specification A.1, 2, and 3 may be modified as follows:

a. Only one of the three auxiliary steam generator feedwater pumps shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability provided the required components are tested prior to startup.

b. The auxiliary steam generator feedwater pump discharge valves of the pump tested in 5a shall be exercised on a monthly basis provided all the discharge valves are tested prior to startup.

B. Acceptance Criteria These tests, except the system flow test, shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have operated and sequenced properly.

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, ' TS 4.10-1 4.10 REACTIVITY ANOMALIES Applicability Applies to potential reactivity anomalies.

Objective To require evaluation of applicable reactivity anomalies within the reactor.

Specification A. Following a normalization of the computed boron concentration as a function of burnup, the actual boron concentration of the coolant shall be compared monthly with the predicted value. If the difference between the observed and predicted steady-state concentrations reaches the equivalent of one percent in reactivity, an evaluation as to the cause of the discrepancy shall be made and reported to the Nuclear Regulatory Commission per Section 6.6 of these Specifications. The provisions of Specification 4.0.4 are not applicable.

8. During periods of POWER OPERATION at greater than 10% of RATED POWER, the hot channel factors identified in Section 3.12 shall be determined during each effective full power month of operation using data from limited core maps. If these factors exceed their limits, an evaluation as to the cause of the anomaly shall be made. The provisions of Specification 4.0.4 are not applicable.

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TS 4.11-1 4.11 SAFETY INJECTION SYSTEM TESTS Applicability Applies to operational testing of the Safety Injection System.

Objective To verify that the Safety Injection System will resp~nd promptly and perform its design functions, if required.

Specification A. The safety injection system shall be demonstrated OPERABLE:

1. By verifying, that on recirculation flow, each low head safety injection pump performs satisfactorily when tested in accordance with Specification 4.0.5.

2. By verifying, that on recirculation flow, each charging pump performs satisfactorily when tested in accordance with Specification 4.0.5.

3. By verifying that each motor-operated valve in the safety injection flow path performs satisfactorily when tested in accordance with Specification 4.0.5.

4. At least once per 18 months, during shutdown, by:

a. Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal. The charging and low head safety injection pumps may be immobilized for this test.

b. Verifying that each of the charging and safety injection pump circuit breakers actuate to its correct position on a safety injection test signal. The charging and low head safety injection pumps may be immobilized for this test.

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TS 4.17-1 4.17 SHOCK SUPPRESSORS (SNUBBERS)

Applicability Applies to all hydraulic and mechanical shock suppressors (snubbers) which are required to protect the reactor coolant system and other safety-related systems. Snubbers excluded from this inspection are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Objective To specify the minimum frequency and type of surveillance to be applied to the hydraulic and mechanical snubbers required to protect the reactor coolant system and other safety-related systems.

Specification Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

A. Visual Inspections

1. Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.17-1. The visual inspection interval of each type of snubber shall be determined based upon the criteria provided in Table 4.17-1.

ML18153D214

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