ML18139C030

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Proposed Tech Spec Changes Re Inservice Insp & Testing
ML18139C030
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/21/1982
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139C028 List:
References
NUDOCS 8209230355
Download: ML18139C030 (21)
v • d • e


Text

4.0 e e TS 4.0-1 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. Specified

time intervals may be adjusted plus or minus 25 percent to accomodate normal test schedules.

4.0.3. Inservice

testing and Inservice Inspection of ASME Code Class 1, 2, and 3 Components and Supports shall be formed 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 NRC pursuant to 10 CFR 50, Section 50.~5a(g)(6)(i).

4.0.4 , All ASME Code Class 1, 2 and 3 Components and Supports shall be repaired or replaced 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 NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

References FSAR Section 12.9 Inservice Inspection FSAR Section 14_.J _Qperational Safety Review -82(f9:i30355

-82092-1 PDR ADOCK 05000280 p PDR e TS 4.0-2 Bases This specification provides that surveillance activities necessary to insure the Limiting Condition for operation are met and will be performed during all operating conditions for which the limiting condition for operation are applicable.

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 conditions.

This specification ensures that inservice inspection and inservice testing of ASME Code Class 1, 2 and 3 components and supports will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50. 55a. Relief from any of the above requirements has been provided in writing to the Commission and is not a part of these Technical Specifications.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precendence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. This specification ensures that all repairs and replacements of ASME Code Class 1, 2, and 3 components are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and addenda as required by 10 CFR 50.55a. Relief from the above requirements has been provided in writing to the Commission and is not part of the Technical Specifications.

* :,1~ . ,. :*. ;,':' **.:.' ' . *., .. ' .. -, .... ~,: ~. '.-.. ,,-...... *: ' TABLE 4.1-2A MINIMUM FREQUENCY FOR EQUIPMENT TESTS DESCRIPTION

1. Control Rod Assemblies
2. Control Room Assemblies
3. Refueling Water Chemical Addition Tank TEST Rod drop times of all full length rods at hot and cold conditions Partial movement of all rods Functional
4. Pressurizer Safety Valves Setpoint 5. Main Steam Safety Valves Setpoint 6. Containment Isolation Trip *Functional
7. Refueling System Interlocks
  • Functional
8. Service Water System *Functional
9. Fire Protection Pump and Functional Power Supply 10. Primary System Leakage 11. Diesel Fuel Supply 12. Boric Acid Piping Heat Tracing Circuits 13. Main Steam Line Trip *Evaluate
  • Fuel Inventory
  • Operational Functional FREQUENCY Each refueling shutdown or after disassembly or maintenance quiring the breech of the Reactor Coolant System integrity Every 2 weeks Each refueling shutdown See specification 4.0.3 See specification 4.0.3 Each refueling shutdown Prior to refueling Each refueling shutdown Monthly Daily 5 days/week Monthly See Specification 4.7 FSAR SECTION REFERENCE 7 7 6 4 10 5 9.12 9.9 9.10 4 8.5 9.1 10 e 3 Cl)

TS 4.2-1 4.2 Structual Integrity of ASME Code Class 1, 2 and 3 components and -supports.

Applicability Applies to inservice inspection of ASME Code Class 1, 2, and 3 components and supports.

Objectives To provide assurance of the continued integrity of ASME Code Class 1, 2, and 3 components and supports.

Specifications A. Inservice Inspection of ASME Code Class 1, 2, and 3 components and supports shall be performed in accordance with specification 4.0.3. In addition, the Reactor Coolant Pump flywheel shall be inspected per recommendation of Regulatory Position C.4.b. of Regulatory Guide 1.14, Revision 1, August 1975. B. The reactor vessel irradiation surveillance capsules shall be removed and examined as follows: Capsule #1 shall be removed and examined at first region refueling.

Capsule #2 shall be removed and examined after five years. Capsule #3 shall be removed and examined after ten years. Capsule #4 shall be removed and examined after twenty years. Capsule #5-8 are spares for complementary or duplicate testing. See Table 4.2-1. The results obtained from these examinations shall be used to update Figure 3.1-1 as required.

TS 4.2-2 BASIS The inspection programs for ASME Code Class 1, 2, and 3 components and supports ensure that the structural integrity will be maintained at an acceptable level throughout the life of the plant. Since each unit was designed and partially constructed without the benefit of Section XI of the ASME Boiler and Pressure Vessel Code, full compliance may not be feasible or practical.

However 9 the inspection program was developed by adopting, insofar as practical, the principles and intent embodied in the Code. The reactor vessel irradiation surveillance program is included to determine the increase in NDT as a result of fast neutron irradiation.

The reactor coolant system heatup and cooldown curves will be adjusted as necessary as required by T.S. 3.lB to assure compliance wit~ the minimum temperature requirement of Appendix C to 10 CFR 50.

,. ~" *,',*'.-"*' *****, ,, .... ~-' ....,,..,.

... , ....... '-,, , ~,-... . . . .. -. " .. **-.. REQUIRED EXAMINATION AREAS Materials Irradiation Surveillance REQUIRED EXAMINATION METHODS Tensile and Charpy V notch (wedge open loading) and Dosimetry TABLE 4.2-1 RV IRRADIATION SURVEILLANCE EXTENT OF EXAMINATION PLANNED DURING FIRST 5-YEAR INTERVAL Capsule 1 shall be removed and examined at the first region replacement.

Capsule 2 shall be examined after 5 years. TENTATIVE INSPECTION DURING 10-YEAR INTERVAL Capsules shall be removed and examined after 10 years REMARKS Capsule 4 shall be removed and examined after 20 years. Capsules 5-8 are extra capsules for complementary or duplicate testing. : I -

e TS 4.3-1 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE TESTS Applicability Applies to requirements for ASME Code Class 1, 2, and 3 System Pressure Tests. In this context, closed is defined as the state of system integrity which permits pressurization and subsequent normal operation after the system has been opened. Objective To specify requirements for ASME Code Class 1, 2, and 3 System Pressure.

Tests following normal operation, modification, or repair. The pressure temperature limits for Reactor Coolant System tests will be in accordance with Figure 3.1-1. Specification A. Inservice inspection, which includes system pressure testing, of ASME Code Class 1, 2, and 3 components 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 NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

  • B. Each time the Reactor Coolant System is closed, the system will be leak tested at a test pressure of not less than the nominal operating pressure in corformance with NDT requirements.

-TS 4.3-2 Basis System pressure testing is performed in order to insure integrity of the system. For normal opening the integrity of the system, in terms of strength, is unchanged.

If, for example, the Reactor Coolant System does not leak at the nominal operating pressure, it will be assumed leaktight for normal operation.

The testing is based on 10 CFR 50.55a and performed pursuant to Section XI of the ASME Code for inservice inspection of Class 1, 2, and 3 components.

e -TS 4.5-1 4.5 SPRAY SYSTEMS TESTS Applicability Applied 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. Test and Frequencies

1. The containment spray pumps shall be tested pursuant to Specification 4.0.3. 2. All inside containment recirculation spray pumps shall be tested pursuant to Specification 4.0.3. 3. The recirculation spray pumps outside the containment shall be tested pursuant to Specification 4.0.3.

TS 4.5-2 4. The weight loaded check valves within the containment in the various subsystems shall be tested pursuant to Specification 4.0.3. 5. All motor operated valves in the containment spray and recirculation spray flow path shall be tested pursuant to Specification 4.0.3. 6. The containment spray nozzles and containment recirculation spray nozzles shall be demonstrated operable at least once per five years coinciding with the closest refueling outage, by performing an air or smoke flow test and verifying each spray nozzle is unobstructed.

7. The spray nozzles in the refueling water storage tank shall be checked for proper functioning in performing the pump test. n. Acceptance Criteria I. A test of a recirculation spray pump shall be considered satisfactory pursuant to Specification 4.0.3. 2. A test of a containment spray pump shall be considered satisfactory pursuant to Specification 4.0.3. A check will be made to determine that no particulate material from the refueling water storage tank clogs the test spray nozzles located in the refueling water storage tank.

e -TS 4.5-3 3. The test of each of the weight loaded check valves shall be considered satisfactory pursuant to Specification 4.0.3. 4. A test of a motor operated valve shall be considered satisfactory pursuant to Specification 4.0.3. 5. The test of the containment spray nozzles and recirculation spray nozzle shall be considered satisfactory if flow through each nozzle can be verified.

6. The test of the spray nozzles in the refueling water storage tank shall be considered satisfactory if the monitored flow rate to the nozzles, when compared to the previously established flow rate obtained with the new nozzles, indicates no appreciable reduction in flow rate. 7. The test of the outside recirculation spray pump shall be considered satisfactory pursuant to Specification

4.0.3. Basis

The 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

  • '* ~-* e TS 4.5-4 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 I
  • used in the containment spray headers. The purpose of the recirculation through the test nozzles is to assure that there is no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles. Due to the physical arrangement of the recirculation spray pumps inside the containment, it is impractical to flow-test them periodically.

These pumps are capable of being operated dry for 60 sec and it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Control Room. Motor current is indicated on an ammeter in the Control Room, and will be compared with readings recorded during preoperational tests to ascertain that no degradation of pump operation has occurred.

The recirculation spray pumps outside the containment have the capability of being dry-run and flow-tested.

The test of an outside recirculation spray pump is performed by closing the suction line valve and the isolation valve between the pump discharge and the containment pen~tration.

This allows *the pump casing to be filled with water and the pump to recirculate water through a test line from the pump discharge to the pump casing. With system flush conducted to remove particulate matter prior to the installation of spray nozzles and with corrosion resistant nozzles and piping, it is not considered credible that a significant number of nozzles would plug ~uring the life of the unit to reduce the effectiveness of the subsystems; e -TS 4.5-5 therefore, provisions to air test the nozzles every five years coinciding with the closest refueling outage is sufficient to indicate that plugging of the nozzles has not occurred.

The spray nozzles in the refueling water storge tank provide means to ensure that there is no particulate matter in the refueling water storage tank and the Containment Spray Subsystems which could plug or cause deterioration of the spray nozzles. The nozzles in the tank are identical to those used on the containment spray headers. The test of the containment spray pumps and recirculation to the refueling water storage will indicate any plugging of the nozzles by a reduction of flow through the nozzles. References

1. Each main steam trip valve shall be demonstrated operable in accordance with Specification 4.0.3. B. Acceptance Criteria 1. A full closure test of main steam trip valves shall be tested pursuant to Specification

4.0.3. Closure

Line shall not exceed a maximum of 5 sec. Basis The main steam trip valves serve to limit an excessive Reactor Coolant System cooldown rate and resultant reactivity insertion following a main steam line

  • TS 4.7-2 break accident.

Their ability to close fully shall be verified in accordance with Specification 4.0.3. A maximum closure time of 5 sec was selected since this is the closure time assumed in the safety evaluation.

Specification A. Tests and Frequency

1. Each motor driven auxiliary steam generator feedwater pump shall be tested for at least 15 minutes pursuant to Specification 4.0.3. 2. The turbine driven auxiliary steam generator feedwater pump shall be flow tested for at least 15 minutes pursuant to Specification 4.0.3. 3~ The auxiliary steam generator feedwater pump discharge valves shall be exercised pursuant to Specification 4.0.3.
  • e TS 4.8-2 4a. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving reactor criticality, the stea.m turbine driven auxiliary feedwater pump shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators.

5. During periods of extended reactor shutdown, with the opposite unit's reactor coolant system above 350°F and 450 psig, the requirements of Specification A. 1, 2, and 3 inay be modified as follows: a. One of the three auxiliary steam generator feedwater pumps shall be tested for at least 15 minutes pursuant to Specification 4.0.3 in order to verify compliance with Specification 3.6.B.l. b. The auxiliary steam generator feedwater pump cross-connect valves shall be tested pursuant to Specification 4.0.3. 6. During periods of extended shutdown of both units, the requirements of Specification A. l, 2, 3 may be waived provided the system is tested prior to startup and the tests specified in A.5 are performed on the opposite unit prior to startup.

e -TS 4.8-3 B. Acceptance Criteria These tests shall be considered satisfactory pursuant to Specification 4.0.3. The system flow test shall be considered satisfactory if the control board indication demonstrates that flow paths exists to each steam generator.

Basis The auxiliary steam generator feedwater pumps will be tested to demonstrate their operability by recirculation to the 110,000 Gallo.n Condensate Storage Tank. The capacity of any one of the three feedwater pumps in conjunction with the water inventory of the steam generators is capable of maintaining the plant in a sa*fe condition and sufficient to cool the unit doW1;1. Proper functioning of the steam turbine admission valve and the ability of the feedwater

  • pumps to start will demonstrate the integrity of the system. Verification of correct operation can be made both from instrumentation within the Main Control Room and direct visual observation of the pumps. References FSAR Section 10.3.1 Main Steam System FSAR Section 10.3.2 Auxiliary Steam System e e 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 respond promptly and perform its design functions, if required.

Specification A. Tests and Frequency

1. System tests shall be performed during reactor shutdowns for refueling.

The test shall be performed in accordance with the following procedure:

With the Reactor Coolant System pressure less than or equal to 450 psig and temperature less than or equal to 350°F, a test safety injection signal will be applied to initiate operation of the system. The charging and low head safety injection pumps may be immobilized for this test.

B. e

  • TS 4.11-2 2. The low head safety injection pumps and charging pumps shall be tested pursuant to Specification 4.0.3. 3. The refueling water storage tank outlet valves shall be tested pursuant to Specification 4.0.3. 4. The accumulator check valves shall be tested pursuant to Specification 4.0.3. 5. All valves required to operate on a safety injection signal shall be tested pursuant to Specification

4.0.3. Acceptance

Criteria 1. The system test will be considered satisfactory if control board indication and/or visual observations indicate that all the appropriate components have received the safety injection signal in the proper sequence.

That is, the appropriate pump breakers shall have been opened and closed, and all valves, required to establish a safety injection flow path to the Reactor Coolant System and to isolate other systems from this flow path, shall have completed their stroke. 2. The pump and valve testing shall be considered satisfactory pursuant to Specification 4.0.3.

I __ *

  • TS 4.11-3 Basis Complete system tests cannot be performed when the reactor is operating because a safety injection signal causes containment isolation.

The method of assuring operability of these systems is therefore to combine systems tests to be performed during refueling shutdowns,*

with more frequent component tests, which can be performed during reactor operation.

The systems tests demonstrate proper automatic operation of the Safety Injection System. A test signal is applied to initiate automatic action and verification' is made that the components receive the safety injection signal in the proper sequence.

The test may be performed with the pumps blocked from starting.

The test demonstrates the operation of the valves, pump circuit breakers, and automatic circuitry.

During reactor operation, the instrumentation which is depended on to initiate safety injection is checked periodically, and the initiating circuits are tested in accordance with Specification 4.1. In addition, the active components (pump and valves) are to be periodically tested to check the operation of the starting circuits and to verify that the pumps are in satisfactory running order. The test interval is determined in accordance with ASME Section XI. The accumulators are a passive safeguard.

In accordance with Specification 4.1 the water volume and pressure in the accumulators are checked periodically.

Reference FSAR Sec~ion 6.2 Safety Injection System

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