ML18143B449

Proposed Tech Specs,Updating Inservice Insp Proposal in Response to NRC 850528 Request for Addl Info

ML18143B449
Person / Time
Site:	Surry
Issue date:	08/30/1985
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18143B448	List: ML18143B447 ML18143B449
References
NUDOCS 8509100238
Download: ML18143B449 (97)

Text

ATTACHMENT 1 TECHNICAL SPECIFICATION CHANGES FOR INSERVICE INSPECTION AND TESTING 8509100238 850830 PDR ADOCK 05000280

. p PDR SURRY POWER STATION UNITS 1 AND 2

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION TITLE 3.15 CONTAINMENT VACUUM SYSTEM 3.16 EMERGENCY POWER SYSTEM 3.17 LOOP STOP VALVE OPERATION 3.18 MOVABLE INCORE INSTRUMENTATION 3.19 MAIN CONTROL ROOM BOTTLED AIR SYSTEM 3.20 SHOCK SUPPRESSORS (SNUBBERS) 3.21 FIRE DETECTION AND SUPPRESSION SYSTEM 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS 3.23 CONTROL AND RELAY ROOM VENTILATION SUPPLY FILTER TRAINS 4.0 SURVEILLANCE REQUIREMENTS 4.1 OPERATIONAL SAFETY REVIEW 4.2 AUGMENTED INSPECTIONS 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE 4.4 CONTAINMENT TESTS 4.5 SPRAY SYSTEMS TESTS 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING 4.7 MAIN STEAM LINE TRIP VALVE 4.8 AUXILIARY FEEDWATER SYSTEM 4.9 EFFLUENT SAMPLING AND RADIATION MONITORING SYSTEM 4.10 REACTIVITY ANOMALIES 4.11 SAFETY INJECTION SYSTEM TESTS 4.12 VENTILATION FILTER TESTS 4.13 DELETED 4.14 DELETED 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE MATERIALS TS ii PAGE TS 3.15-1 TS 3.16-1 TS 3.17-1 TS 3.18-1 TS 3.19-1 TS 3.20-1 TS 3.21-1 TS 3.22-1 TS 3.23-1 TS 4.0-1 TS 4.1-1 TS 4.2-1 TS 4.3-1 TS 4.4-1 TS 4.5-1 TS 4.6-1 TS 4.7-1 TS 4.8-1 TS 4.9-1 TS 4.10-1 TS 4.11-1 TS 4.12-1 TS 4.15-1 TS 4.16-1

TS 4.0-1 4.0 SURVEILLANCE REQUIREMENTS 4.0.1 4.0.2 4.0.3 Surveillance Requirements provide for testing, calibrati~g, 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.

Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

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a.

Inservice 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 Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR 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 by testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Applicable Addenda Terminology for Inservice Inspection and Testing Activities Monthly Quarterly or Every 3 Months Cold Shut Down Refueling Shut Down Inspection Period Inspection Interval TS 4.0-2 Required Frequencies for Performing Inservice Inspection and Testing Activities At least once per 31 days At least once per 92 days At least once per CSD At least once per RSD Per Table -

IWB, IWC-2412-1 Per IWA-2400

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 4.0-3 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 surveillarice activities, beyon,d those specified in the nominal surveillance interval.

These tolerances are necessary. to provide operational flexibilfty.

because of sch~<l~ling

• arid performance considerations.

The

• phrase "at leastll associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.

This specification ensures *. that inservice inspection, repai.rs, arid replacements of ASME

• Code. Class 1, 2, and 3 components and inservice testing of _ASME Code Class 1, 2, and 3 pumps and valves identified per NRC submittal 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 50.55a.

Relief from any 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 activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable

TS 4.0-4 Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiquities relative to the frequencies for performing the required inservice inspection and testing activities.

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 provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

Description

1.

Control Rod Assemblies

2.

Control Rod Assemblies

3.

Refueling Water Chemical Addition Tank

4.

Pressurizer Safety Valves

5.

Main Steam Safety Valves

6.

Containment Isolation Trip

7.

Refueling System Interlocks

8.

Service Water System

9.

Fire Protection Pump and Power Supply

10.

Primary System Leakage

11.

Diesel Fuel Supply

12.

Boric Acid Piping Heat Tracing Circuits

13.

Main Steam Line Trip TABLE 4.1-2A MINIMUM FREQUENCY FOR EQUIPMENT TESTS Test Rod drop times of all full length rods at hot conditions Partial movement of all rods Functional Setpoint Setpoint

• Functional

• Functional

• Functional Functional

• Evaluate

• Fuel Inventory

• Operational Functional (1) Full closure Frequency Each refueling shutdown or after disassembly or maintenance requiring the breach of the Reactor Coolant System integrity Every 2 weeks Each refueling shutdown Per TS 4.0.3 Per TS 4.0.3 Each refueling shutdown Prior to refueling Each refueling shutdown Monthly Daily 5 days/week Monthly (1) Before each startup FSAR Section Reference 7

7 6

4 10 5

9.12 9.9 9.10 4

8.5 9.1 10 1-3 Ul

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TABLE 4.l-3A UNIT 1 MINIMUM FREQUENCIES FOR FLUSHING SENSITIZED PIPE Flush Flow Path - General Description

1.

From C.S. Pump CS-P-lA to M.O.

Isolation Valves

2.

From C.S. Pump CS-P-lB to M.O.

Isolation Valves

3.

From L.H.S.I. Pump, SI-P-lA, Discharge Line to MOV 863A

4.

S.I. line, from charging pump discharge loop fill header to containment missile barrier, for flow to:

a.

R.C. hot leg loop 1

b.

R.C. hot leg loop 2

c.

R.C. hot leg loop 3

5.

S.I. line, from charging pump discharge header to containment missile barrier, for flow to:

a.

R.C. cold leg loop 1

b.

R.C. cold leg loop 2

c.

R.C. cold leg loop 3 Minimum Flush Duration 15 minutes 20 minutes 20 minutes 15 minutes 10 minutes 15 minul;es 5 minutes 5 minutes 5 minutes Frequency Monthly Monthly Monthly Monthly Monthly Monthly Monthly Monthly Monthly Remarks Run separately or run in conjunction with or immediately after pump test required by Specification 4.5.A.l Run separately or run in conjunction with or immediately after pump test required by Specification 4.5.A.l Run separately or run in conjunction with or immediately after pump test required by Specification 4.11.B.1 Flushes to be performed only when R.C. System pressure is

> 1500 psig.

Flushes to be performed only when R.C. System pressure is

> 1500 psig.

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TABLE 4.l-3B UNIT 2 MINIMUM FREQUENCIES FOR FLUSHING SENSITIZED PIPE Flush Flow Path - General Description

1.

From C.S. Pump 2-CS-P-lA to M.O. Isolation Valves

2.

From C.S. Pump 2-CS-P-lB to M.O. Isolation Valves

3.

From L.H.S.I. Pump, 2-SI-P-lA, Discharge Line to MOV 2-863A

4.

6" S.I. line, from L.H.S.I. pumps to containment missile barrier, for flow to:

a.

R.C. hot leg loop 1

b.

R.C. hot leg loop 2

c.

R.C. hot leg loop 3

5.

S.I. line, from charging pump discharge header to containment missile barrier, for flow to:

a.

R.C. cold leg loop 1

b.

R.C. cold leg loop 2

c.

R.C. cold leg loop 3 Minimum Flush Duration 20 minutes 15 minutes 20 minutes 35 minutes 35 minutes 35 minutes 5 minutes 5 minutes 5 minutes Frequency Monthly Monthly Monthly Monthly Monthly Monthly Monthly Monthly Monthly Remarks Run separately or run in conjunction with or immediately after pump test required by Specification 4.5.A.l Run separately or run in conjunction with or immediately after pump test required by Specification 4.5.A.l Run separately or run in conjunction with or immediately after pump test required by Specification 4.11.B.1 Flushes to be performed only when R.C. System pressure is

> 1500 psig.

Run separately or run in conjunction with or immediately after pump test required by Specification 4.11.B.1 Flushes to be performed only when R.C. System pressure is

> 1500 psig.

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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 4.0.3.

B.

The normal inspection interval is 10 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

TS 4.2-2 components and supports.

Certain components, under Miscellaneous Inspec-tions 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.

Sensitized stainless steel augmented inspections were added to assure piping integrity of this classification.

Item 2.1 ASME Class 1 sensitized stainless steel piping will be inspected at three times the frequency required by the Code.

Visual inspections will be conducted, while the piping is pressurized by the procedures defined in Table 4.1-3 of Technical Specification 4.1 concerning flushing of sensitized stainless steel piping.

Item 2.2 Sensitized stainless steel piping designated ASME Class 2 or not subject to Section XI of the ASME Code, will undergo visual and surface examin-ation.

The containment and recirculation spray rings, which are located in the overhead of the containment, will be visually inspected.

Additionally, sections of the piping will be examined by liquid penetrant inspection when the piping is visually inspected.

At least 25 percent of the examinations shall have been completed by the expiration of one-third of the inspection interval and at least 50 percent shall have been completed

TS 4.2-3 by the expiration of two-thirds of the inspection interval.

The remain-ing required examinations shall be completed by the end of the inspection interval.

All other piping included in Item 2.2 will be visually inspected at least every two years.

Sections of this piping will be examined by liquid penetrant inspection when the piping is visually inspected.

For the required visual inspection, the piping will be pressurized by the procedures defined in Table 4.1-3 of Technical Specification 4.1 concerning flushing of sensitized stainless steel piping.

SECTION A, MISCELLANEOUS INSPECTIONS Item No.

1.1 Required Examination Area Materials Irradiation Surveillance Required Examination Methods Tensile and Charpy V notch (wedge open loading) and dosimetry as necessary to insure surveil-lance.

TABLE.

Tentative Inspection During 10-Year Interval Capsules shall be removed and examined after 10 years. (See Notes 1 and 2)

Note 1:

1 year corresponds to 1 year effective full power operation.

Remarks Capsule #1 = First refueling Capsule #2 = At five years Capsule 113 = At 10 years Capsule 114 = At 20 years Capsule tlS-8 = Are spares for complemen-tary or duplicate testing.

Note 2:

The results obtained from these examinations shall be used to update Figure 3.1-1 as required.

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SECTION A.

MISCELLANEOUS INSPECTIONS Item No.

1.2 1.3 Required Examination Area Primary Pump Flywheel Low Pressure Turbine Rotor Required Examination Methods See remarks Visual and Magnetic Particle or Dye Penetrant SECTION B.

SENSITIZED STAINLESS STEEL 2.1.1 2.1.2 Circumferential and longitudinal pipe welds and branch pipe connections larger than 4 inches in diameter.

Circumferential and longitudinal pipe welds and branch pipe connections.

Visual and Volumetric Visual TABLE Tentative Inspection During 10-Year Interval See remarks 100% of blades every 5 years By the end of the interval, a cumulative 75% of the circumferen-tial welds in the piping system would have been examined, including one foot on any longitudinal weld on either side of the butt welds.

By the end of the interval a cumulative 100% of the welds and pipe branch connections would be examined a minimum of three times.

Remarks Examination to be con-ducted in accordance with regulatory position C. 4. b of regulatory guide 1.14 Rev.I, August 1975.

None.

A minimum of 5% of the welds will be examined every 1-2/3 years (generally each normal refueling outage).

See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7, p. 10).

A minimum of 50% of the welds will be examined every 1-2/3 years (generally, each normal refueling outage)

See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7, p. 10).

SECTION B.

SENSITIZED STAINLESS STEEL Item No.

2.1.3 2.2.1 Required Examination Area Socket welds and pipe branch connections welds 4 inches in diameter and smaller Containment and Recirculation Required Examination Methods Visual and Surface Visual and Surface TABLE Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 75% of the circumferential welds in the piping system and 75%

of the pipe branch connec-tions welded joints would be examined.

(See Remarks)

Remarks A minimum of 5% of the circumferential welds and 5% of the pipe branch connection welded joints will be examined every 1-2/3 years (generally each normal refueling outage).

See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7, p. 10).

At least 25 percent of the examinations shall have been completed by the expiration of one-third of the inspection interval and at least 50 percent shall have been completed by the expira-tion of two-thirds of the inspection interval.

The rema1n1ng required examinations shall be completed by the end of the inspection interval.

Surface examination will include 6 patches (each 9 inches square) evenly distributed around each spray ring.

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SECTION B.

SENSITIZED STAINLESS STEEL (continued)

Item No.

2.2.2 Required Examination Area Remaining sensitized stainless steel piping Required Examination Methods Visual and Surface Tentative Inspection During 10-Year Interval (See Remarks)

Remarks The piping would be in-spected every two years.

The inspection will in-clude 100% of the piping by visual examination.

Surface examination will include a strip one inch wide and one foot long located on each piping bend.

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TS 4.2-8 (Pages TS 4.2-8 through TS 4.2-35 have been deleted.)

TS 4.3-1 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE TESTS Applicability Applies to requirement 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 NRG 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 +100 psi in conformance 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 plus 100 psi, 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.

TS 4.3-3 (Pages TS 4.3-3 and TS 4.3-4 have been deleted.)

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.

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 recircu-lation 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 5 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 containment spray pump test.

B.

Acceptance Criteria

1.

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

BASIS TS 4.5-3 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.

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 satis-factory 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 appre-ciable reduction in flow rate.

7.

The test of the outside recirculation spray pump shall be considered satisfactory pursuant to Specification 4.0.3.

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 contain-

TS 4.5-4 ment 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 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 seconds 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 pre-operational 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 penetration.

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

TS 4.5-5 nozzles would plug during the life of the unit to reduce the effective-ness of the subsystems; therefore provisions to air-test the nozzles every 5 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 storage 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 identi-cal to those used on the containment spray headers.

The flow 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 FSAR Section 6.3.1, Containment Spray Pumps FSAR Section 6.3.1, Recirculation Spray Pumps

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.

B.

Basis Tests and Frequencies

1.

Each main steam trip valve shall be demonstrated operable in accordance with Specification 4.0.3., prior to each startup.

Acceptance Criteria

1.

A full closure test of main steam trip valves shall be tested pursuant to Specification 4.0.3.

Closure time shall not exceed a maximum of 5 seconds.

The main steam trip valves serve to limit an excessive Reactor Coolant System cooldown rate and resultant reactivity insertion following a main steam line break accident.

Their ability to close fully shall be veri-fied in accordance with Specification 4.0.3.

A maximum closure time of 5 seconds was selected since this is the closure time assumed in the safety evaluation.

TS 4.7-2 (This page has been deleted.)

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

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

Specification A.

Tests and Frequency

1.

Each motor driven auxiliary steam generator feedwater pump shall be tested for at least 15 minutes pursuant to Specifi-cation 4.0.3.

2.

The turbine driven auxiliary steam generator feedwater pump shall be tested for at least 15 minutes pursuant to Specifi-cation 4.0.3.

3.

The auxiliary steam generator feedwater pump discharge valves shall be exercised pursuant to Specification 4.0.3.

B.

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 steam 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 may 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.I, 2, and 3 may be waived providing the system is tested prior to startup and the tests specified in A.5 are performed on the opposite unit prior to startup.

Acceptance Criteria These tests shall be considered satisfactory pursuant to Specification 4.0.3

• TS 4.8-3 The system flow test shall be considered satisfactory if the control board indication demonstrates that flow paths exist to each steam generator.

Basis The auxiliary steam generator feedwater pumps will be tested to demonstrate their operability by recirculation to the 110,000- gallon 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 safe condition and sufficient to cool the unit down.

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

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.

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.

s.

Fill valves required to operate on a safety injection signal shall be tested pursuant to Specification 4.0.3.

B.

Basis TS 4.11-2 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 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.

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 system tests to be performed during refueling shutdowns, with more frequent component tests, which can be performed during reactor operation.

The system 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 injec-tion 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 (pumps 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

TS 4.11-3 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 Section 6.2, Safety Injection System

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ATTACHMENT 2 DESCRIPTION OF CHANGE AND SAFETY EVALUATION SURRY POWER STATION UNITS 1 AND 2

DESCRIPTION OF CHANGES As required by 10CFR50.55a(g)5ii, changes to Technical Specifications are required if the revised inservice inspection program for the facility con-flicts with the current Technical Specifications.

Changes will be identified as one of three types:

1)

More restrictive than present Technical Specifications

2)

Less restrictive than present Technical Specifications

3)

Remains essentially the same (format change only)

The specifics of each type of change and evaluation of each change is as follows:

Page TS 4.0-1 (Specification 4.0.1) "Surveillance Requirements".

Speci-fication modified into an outline form in order that it may be refer-enced. (Remains essentially the same.)

Page TS 4.0-1 (Specification 4.0.2)

"Surveillance Time Interval'i.

Specificat_ion modified into

• an outline form in order that it may be referenced.

(Remains essentially the same.)

Page TS 4.0-1 (Specification 4.0.3) "Inservice Inspection and Testing".

Specification added to incorporate standard reference Section XI of the ASME Boiler and Pressure Vessel Code.

Periodic update of referenced code would be in accordance with 10CFR50.55a requirements.

(More restrictive than present specifications).

Page Table 4. l-2A, Table 4. l-3A, and Table 4. l-3B, "Test and Flushing Frequencies". Several changes to tables to meet code requirements and facilitate testing.

Table 4.l-2A (4)

Table 4.1-2A (5)

Table 4.l-2A (13)

Table 4.l-3A (1),

(2), (3) and Table 4.l-3B, C.

(2), (3), and (4)

Main steam safety valves tested to code frequency.

(Less restrictive than present Technical Specifi-cations.)

Pressurizer safety valves tested to code frequency.

(Less restrictive than present Technical Specifi-cation.)

Main steam line trip valves tested for full closure prior to each startup due to difficulty in controll-ing partial closure.

(More restrictive than present Technical Specification.)

Remarks changed to accommodate quarterly testing allowed by code for listed pumps.

Flushing will still be required monthly.

(Essentially the same.)

Page TS 4. 2-1 (Specification 4. 2) "Augmented Inspections". Miscellaneous inspections and sensitized stainless steel inspections maintained from old Technical Specifications.

Use of the ASME Section XI code created unnecessary duplication within old T. S.

Comparison of TS requirements vs. code requirements given on individual item basis, as follows:

TECH SPEC ITEM Item No.

1.1 Category A

CODE EQUIVALENT ITEM NO.

Bl.10 Bl.11 Bl.12 CATEGORY BA Required Examination Areas Longitudinal and circumferential shell welds in core region 2ND INTERVAL PARTS EXAMINED SHELL WELDS CIRCUMFERENTIAL LONGITUDINAL (ONE BELTLINE REGION WELD EACH)

(SELECT WELD LOCATED AT A DESIGN STRUCTURAL DISCONTI.NUITY, IF.

ANY.) (FIG. NO.

IWB2500-l,2)

Required Examination Methods Volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 0%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

Tentative Inspection During 10-Year Interval 5% of the length of the circumferential welds; 10% of the length of the longitudinal welds EXTENT OF EXAM FOR INTERNAL 100% OF WELD LENGTH COMMENTS:

1.

CURRENT NEUTRON FLUENCE UNIT 1, 6.08339 x 1018 n/cm2, UNIT 2, 6.30491 x 1018 n/cm2 (4/16/85).

2.

GENERAL SELECTION DIFFERENCES WITH ACTUAL EXAMINATION AREA INCREASING, CLASSIFIED MORE RESTRICTIVE.

Remarks The required examinations may be made at or near the end of the 10-year inspection interval.

When the longitudinal and cir-cumferential weld have received an exposure to y9utron fluence in excess of 10 nvt (E of 1 Mev or above), the lengtR of the weld in the high fluence region to be examined shall be increased to 50 per cent.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

TECH SPEC ITEM Item No.

1. 2 Category B

CODE EQUIVALENT ITEM NO.

Bl.20 CATEGORY BA Required Examination Areas Longitudinal and circumferential welds in shell (other than those of Category A and C) and meridional and circumferen-tial seam welds in bottom head and closure head (other than those of Category C)

Required Examination Methods Volumetric 2ND INTERVAL EXAMINATION PARTS EXAMINED METHOD HEAD WELDS VOLUMETRIC CIRCUMFERENTIAL MERIDIONAL (ACCESSIBLE LENGTH OF ONE WELD EACH.) (FIG.

NO. IWB 2500-3)

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 0%

NORMAL PERIOD REQUIREMENTS 1ST: 16%-34%

2ND: 50%-67%

3RD: 100%

Tentative Inspection During 10-Year Interval 5% of the length of the circumferential welds; 10% of the length of the longitudinal welds EXTENT OF EXAM FOR INTERNAL 100% OF WELD LENGTH COMMENTS:

1.

NO OTHER LONGITUDINAL AND CIRCUMFERENTIAL WELDS EXIST OTHER THAN THOSE IN ITEM 1.1 AND 1.3.

2.

INSPECTION AREA INCREASED.AND DEFERRAL LIMITED TO BOTTOM HEAD, CONSIDERED MORE RESTRICTIVE.

Remarks The required examinations may be made at or near the end of the 10-year inspection interval.

REMARKS DEFERRAL OF THE INSPECTION TO END OF INTERVAL.

PERMISSIBLE FOR BOTTOM HEAD ONLY.

TECH SPEC ITEM Item

• No.

1.3 Category C

CODE EQUIVALENT ITEM NO.

Bl.30 Bl.40 CATEGORY BA Required Examination Areas Vessel-to-flange and head-to-flange circum-ferential welds 2ND INTERVAL PARTS EXAMINED SHELL-TO-FLANGE WELD HEAD-TO-FLANGE WELD (FIG. NO.

IWB-2500-4,5)

Required Examination Methods Volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the length of the circumferential welds NORMAL PERIOD REQUIREMENTS 1ST: 50%; 3RD: 50%

Tentative Inspection During 10-Year Interval 100% of the length of the circumferential welds EXTENT OF EXAM FOR INTERNAL 100% WELD LENGTH COMMENTS:

1.

SHELL-TO-FLANGE EXAMS CONDUCTED IN CONJUNCTION WITH NOZZLE EXAMINATIONS OF CATEGORY B-D.

Remarks Both of these welds are available for examination during normal refueling operations.

REMARKS PARTIAL DEFERRAL, IF PARTIAL EXAMINATIONS CONDUCTED ON FLANGE FACE, THE REMAINING VOLUMETRIC EXAMINATIONS REQUIRED TO BE CONDUCTED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR END OF INSPECTION INTERVAL.

2.

MINOR DIFFERENCES, ADDITION OF SURFACE EXAMINATION FOR HEAD-TO-FLANGE WELD CONSIDERED MORE RESTRICTIVE.

USE OF PARTIAL DEFERRAL CONSIDERED LESS RESTRICTIVE.

TECH SPEC ITEM Item No.

1.4 Category D

CODE EQUIVALENT ITEM NO.

B3.90 B3.100 CATEGORY B-D Required Examination Areas Primary nozzle-to vessel welds and nozzle-to-vessel inside radiused section 2ND INTERVAL PARTS EXAMINED REACTOR VESSEL NOZZLE-TO-VESSEL WELDS NOZZLE-TO-INSIDE RADIUS SECTION (ALL NOZZLES)

(FIG. NO.

IWB-2500-7)

Required Examination Methods Volumetric EXAMINATION METHOD 1ST: 25-50%,

THEN 100% BY END OF 3RD PERIOD TABLE 4.2-1 Extent of Examination Planned During First

• s-Year Interval 100%*of coverage of a coolant outlet nozzle-to-shell weld and inner nozzle radii NORMAL PERIOD REQUIREMENTS INCLUDES NOZZLE-TO-VESSEL WELD AND ADJA-CENT AREAS OF NOZZLE AND VESSEL Tentative Inspection During 10-Year Interval 100% of the remaining coolant outlet nozzle-to-shell welds and inner radius sections and 100% of the coolant inlet nozzles-to-shell welds and radius sections EXTENT OF EXAM FOR INTERNAL IF EXAMINATIONS ARE CONDUCTED FROM INSIDE THE COMPONENT AND THE NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRA-SONIC METHOD FROM THE NOZZLE BORE, THE REMAIN-ING EXAMS REQUIRED TO BE CONDUCTED FROM THE SHELL MAY BE PERFORMED AT OR NEAR THE END OF THE INSPECTION INTERVAL.

COMMENTS:

GENERAL DIFFERENCES IN TREATMENT OF NOZZLES.

INLET NOZZLES NOW CONSIDERED MORE RESTRICTIVE, OUTLET NOZZLES LESS RESTRICTIVE IN AREA OF INSPECTION COMPLETION WITH RESPECT TO TIME INTERVAL.

Remarks The coolant inlet nozzles-to-shell welds and radius sections will be examined at the same time as the welds in Category A.

REMARKS

TECH SPEC ITEM Item No.

1.5 Category E-1 CODE EQUIVALENT ITEM NO.

Bl4.10 CATEGORY B-0 Required Examination Areas Vessel penetra-tions, including control rod drive penetrations and control rod housing pressure boundary welds 2ND INTERVAL PARTS EXAMINED REACTOR VESSEL WELDS IN CRD HOUSING (FIG. NO. IWB-2500-18)

Required Examination Methods Volumetric EXAMINATION METHOD VOLUMETRIC OR SURFACE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 0%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100% (OF 10%)

Tentative Inspection During 10-Year Interval 25%

EXTENT OF EXAM FOR INTERNAL 10% OF PERIPHERAL CRD HOUSINGS COMMENTS:

ONLY WELDS IN CRD HOUSING CONSIDERED IN 80W80 CODE, THEREFORE LESS RESTRICTIVE.

Remarks No meaningful volumetric examina tions can be performed on the control rod drive penetrations at this time.

Volumetric exam-ination of the instrument penetrations in the. bottom head will be performed dependent upon development of acceptable equip-ment.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

TECH SPEC ITEM Item No.

1. 6 Category E-2 CODE EQUIVALENT ITEM NO.

B4.10 B4.ll B4.12 CATEGORY B-3 Required Ex_amina t ion Areas Vessel penetra-tions, including control rod drive penetrations and control rod hous-ing pressure boundary welds 2ND INTERVAL PARTS EXAMINED PARTIAL PENETRA-TION WELDS VESSEL NOZZLES CONTROL ROD DRIVE NOZZLES B4.13 INSTRUMENTATION NOZZLES (EXTERNAL SUR-FACES)

COMMENTS:

PRESSURE TEST ESSENTIALLY THE SAME.

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-2 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 0%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

Tentative Inspection During 10-Year Interval 25%

EXTENT OF EXAM FOR INTERNAL 25%

Remarks The examination will be a visual examination for evidence of leaking at the time of the system hydrostatic test at or near the end,of the inspection interval.

REMARKS EXAMINATION TO BE CONDUCTED WITH CORRESPONDING PRESSURE TEST.

TECH SPEC ITEM Item No.

1. 7 Category F

CODE EQUIVALENT ITEM NO.

BS.10 CATEGORY B-F Required Examination Areas Primary nozzles to safe and welds 2ND INTERVAL PARTS EXAMINED REACTOR VESSEL NOMINAL PIPE SIZE

>4 IN.

NOZZLE-TO-SAFE END BUTT WELDS (ALL)

(FIG. NO. IWB 2500-8)

Required Examination Methods Visual and surface volumetric EXAMINATION METHOD VOLUMETRIC, SURFACE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 100% of the dissimilar metal weld on one coolant outlet nozzle will be volumetrically examined NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

COMMENTS:

1.

STATION PROCEDURE REQUIRES A VISUAL PRIOR TO CONDUCTING A SURFACE EXAM.

Tentative Inspection During 10-Year Interval 100% of the remaining coolant outlet nozzle dissimilar metal welds and 100% of the coolant inlet nozzle dissimilar metal welds EXTENT OF EXAM FOR INTERNAL 100% ALL WELDS Remarks The dissimilar metal welds of each nozzle will be volume-trically examined at the same time as the nozzle-to-shell weld, as Bpecified in Category D.

REMARKS THE EXAMINATIONS MAY BE PER-FORMED COINCIDENT WITH THE VESSEL NOZZLE EXAMINATION REQUIRED BY EXAMINATION CATEGORY B-D.

2.

GENERAL DIFFERENCES IN INITIAL EXAMINATION DISTRIBUTION, BUT ESSENTIALLY THE SAME.

TECH SPEC ITEM Item No.

1.8 Category G-1 CODE EQUIVALENT ITEM NO.

B6.10 B6.20 B6.30 CATEGORY B-G-1 Required Examination Areas Closure studs and nuts 2ND INTERVAL PARTS EXAMINED CLOSURE HEAD NUTS CLOSURE STUDS, IN PLACE CLOSURE STUDS, WHEN REMOVED (FIG. NO. 2500-

12)

Required Examination Methods Volumetric and visual or sur-face EXAMINATION METHOD SURFACE VOLUMETRIC SURFACE AND VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Y.ear Interval 33%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval 100%

EXTENT OF EXAM FOR INTERNAL 100% ALL BOLTS, STUDS, NUTS COMMENTS:

ESSENTIALLY THE SAME EXAMINATION REQUIREMENTS, DEFERRAL WOULD BE LESS RESTRICTIVE.

Remarks Vessel studs and nuts would be inspected volumetrically and by surface techniques as required.

The ligaments of the vessel flange would be examined at the same time as the flange welds.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

TECH SPEC ITEM Item No.

Category

1. 9 G-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Ligaments between threaded stud holes 2ND INTERVAL PARTS EXAMINED Required Examination Methods Volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the vessel-to-flange bolt ligaments will be examined NORMAL PERIOD REQUIREMENTS COMMENTS:

NO EXAMINATION EXISTS IN 80W80 CODE, THEREFORE LESS RESTRICTIVE.

Tentative Inspection During 10-Year Interval 100% of the vessel flange bolt ligaments will be examined EXTENT OF EXAM FOR INTERNAL Remarks The ligaments will be examined at the same time as the flange weld of Item No. 1.3.

REMARKS

• ~,

TECH SPEC ITEM Item No.

1.10 Category G-1 CODE EQUIVALENT ITEM.

NO.

B6.50 CATEGORY B-G-1 Required Examination Areas Closure washers, bushings 2ND INTERVAL PARTS EXAMINED CLOSURE WASHERS, BUSHINGS (SUR-FACES)

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-1 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval 100%

EXTENT OF

,EXAM FOR INTERNAL 100%

ALL WASHERS, BUSHINGS COMMENTS:

ESSENTIALLY THE SAME EXAMINATION REQUIREMENTS, DEFERRAL WOULD BE LESS RESTRICTIVE.

Remarks None.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

TECH SPEC ITEM Item No.

1.11 Category G-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD

.TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no pressure retaining bolts less than 2 inches on the Surry Reactor vessels.

REMARKS COMMENTS:

NO PRESSURE RETAINING BOLTING LESS THAN 2 INCHES EXISTS ON THE SURRY REACTOR VESSEL.*

CODE REQUIREMENTS, CATEGORY B-G-2, ARE ESSENTIALLY THE SAME HOWEVER.

TECH SPEC ITEM Item No.

1.12 Category M

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Internally welded vessel supports 2ND INTERVAL PARTS EXAMINED Required Examination Methods Volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS COMMENTS:

THESE WELDS STILL COVERED BY THE EXAMINATIONS OF CATEGORY B-D.

Tentative Inspection During 10-Year Interval (See remarks)

EXTENT OF EXAM FOR INTERNAL Remarks These welds are covered by the examinations of Category D.

REMARKS

TECH SPEC ITEM Item No.

1.13 Category I-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Closure head cladding 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and surface or volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 2 patches NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval 6 patches EXTENT OF EXAM FOR INTERNAL COMMENTS:

NO CORRESPONDING EXAMINATION REQUIREMENT IN THE 80W80 CODE, CONSIDERED LESS RESTRICTIVE.

Remarks During the 10-year period, at least 6 patches (each 36 square inches) evenly distributed in the vessel head would be examined.

REMARKS

TECH SPEC ITEM Item No.

1.14 Category I-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Vessel cladding 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval None NORMAL PERIOD REQUIREMENTS COMMENTS:

NO CORRESPONDING EXAMINATION IN THE 80W80 CODE, CONSIDERED LESS RESTRICTIVE.

Tentative Inspection During 10-Year Interval 6 patches EXTENT OF EXAM FOR INTERNAL Remarks During the 10-year period, at least 6 patches (each 36 square inches) evenly distributed in the vessel head would be visually inspected.

REMARKS

TECH SPEC ITEM Item No.

1.15 Category M

CODE EQUIVALENT ITEM NO.

Bl3.10 B13.30 CATEGORY B-N-1 B-N-2 B-N-3 Reguired Examination Areas Interior surfaces and internals and integrally welded internal supports Reguired Examination Methods Visual 2ND INTERVAL EXAMINATION PARTS EXAMINED METHOD REACTOR VESSEL VISUAL, VT-3 VESSEL INTERIOR (ACCESSIBLE AREAS ABOVE AND BELOW REACTOR CORE MADE ACCESSIBLE DURING NORMAL REFUELING)

REACTOR VESSEL VISUAL, VT-3 CORE SUPPORT STRUCTURE ACCESSIBLE WELDS (STRUCTURE REMOVED)

ACCESSIBLE VISUAL, VT-3 SURFACES (STRUCTURE REMOVED)

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval A critical examination will be made of the interior surfaces made available by normal refueling operations at the 1st refueling cycle.

This will be repeated at the 4th refueling cycle with the amount of the inspection being dependent u~on results of the 1st inspection and that made on other pressurized-water systems.

NORMAL PERIOD REQUIREMENTS 1ST: 100%

2ND: 100%

3RD: 100%

1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval The inspection made at the 4th refueling cycle will be repeated at the 7th and 10th refueling cycle EXTENT OF EXAM FOR INTERNAL 100% EACH PERIOD ALL WELDS ALL SURFACES Remarks The examination will include internal support attachments welded to the vessel whose.

failure may adversely affect core integrity provided these are available for visual examination by components removed during normal refueling operations.

REMARKS NONE.

DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

COMMENTS:

VESSEL INTERIOR EXAMINATION ESSENTIALLY THE SAME (REFUELING VS. PERIOD), CORE SUPPORT EXAM MORE RESTRICTIVE

• TECH SPEC ITEM Item No.

2.1 Category B

CODE EQUIVALENT ITEM NO.

B2.10 B2.11 B2.12 CATEGORY B-B Required Examination Areas Longitudinal and circumferential welds 2ND INTERVAL PARTS EXAMINED PRESSURIZER SHELL-TO-HEAD WELDS CIRCUMFERENTIAL (ALL WELDS)

LONGITUDINAL (IFT. OF WELD WHICH INTERSECTS CIRCUMFERENTIAL WELD)

(IWB-2500-1,2)

Required Exainination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 5% of the length of the circumferential weld joining the lower head to the barrel section and 10% of the length of the adjoin-ing longitudinal weld would be examined.

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval By the end of the 10-year period, 10%

of the length of the longitudinal and 5% of the length of the circumferential weld would be inspected.

EXTENT OF EXAM FOR INTERNAL 100% (CIRCUMFERENTIAL)

!FT (LONGITUDINAL)

Remarks None.

REMARKS NONE COMMENTS:

1.

RELIEF REQUEST SR-5, SHELL-TO-TOP HEAD, CIRCUMFERENTIAL WELD (7) UNIT 2 INACCESSIBLE DUE TO INSULATION SUPPORT RING.

VISUAL (VT-2)

SUBSTITUTED.

2.

CIRCUMFERENTIAL CONSIDERED MORE RESTRICTIVE (REMAINING), LONGITUDINAL LESS RESTRICTIVE.

TECH SPEC ITEM Item No.

2.2 Category D

CODE EQUIVALENT ITEM NO.

BJ.110 BJ.120 CATEGORY B-D Required Examination Areas Nozzle-to-vessel welds Required Examination Methods Visual and volumetric 2ND INTERVAL EXAMINATION PARTS EXAMINED METHOD PRESSURIZER VOLUMETRIC NOZZLE-TO-VESSEL WELDS NOZZLE INSIDE RADIUS SECTION (INCLUDES NOZZLE-TO-VESSEL WELD AND ADJACENT

. AREAS OF NOZZLE AND VESSEL.) FIG.

NO. IWB-2500-?(d)

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

COMMENTS:

EXAMINATION CONSIDERED MORE RESTRICTIVE SINCE NO EXAM PREVIOUSLY REQUIRED.

Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL ALL NOZZLES Remarks There are no nozzle-to-head welds, as the nozzles are integrally cast with the heads.

Instrument and sample nozzles are included in Category E.

REMARKS NOZZLES ARE INTEGRALLY CAST.

IF EXAMINATIONS ARE CONDUCTED FROM INSIDE THE COMPONENT AND THE NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE REMAINING SHELL EXAMS MAY BE CONDUCTED AT OR NEAR THE END OF THE INSPECTION INTERVAL.

TECH SPEC ITEM Item No.

2.3 Category E-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Neater connec-tions 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and surface EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval (See remarks)

EXTENT OF EXAM FOR INTERNAL COMMENTS:

NO SURFACE EXAMINATION CURRENTLY REQUIRED BY 80W80 CODE, THEREFORE REMAINS THE SAME.

Remarks These connections are considered in Item 2.4.

REMARKS

TECH SPEC ITEM Item No.

2.4 Category E-2 CODE EQUIVALENT ITEM NO.

B4.20 CATEGORY B-E Required Examination Areas Neater connec-tions 2ND INTERVAL PARTS EXAMINED PRESSURIZER HEATER PENETRA-TION WELDS (EXTERNAL SUR-FACES)

Required Examination Methods Visual and surface EXAMINATION METHOD VISUAL, VT-2 COMMENTS:

EXAMINATION REQUIREMENTS REMAINS THE SAME.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50%-67%

3RD: 100%

(of 25%)

Tentative Inspection During 10-Year Interval (See remarks)

EXTENT OF EXAM FOR INTERNAL 25% OF THE PENETRATIONS Remarks These connections are considered in Item 2.4.

REMARKS CONDUCTED WITH PRESSURE TEST.

TECH SPEC ITEM Item No.

Category F

CODE EQUIVALENT ITEM NO.

B5.10 CATEGORY B-F Required Examination Areas Pressure contain-ing dissimilar metal welds 2ND INTERVAL PARTS EXAMINED PRESSURIZER NOMINAL PIPE SIZE

>4 IN.

NOZZLE-TO-SAFE END BUTT WELD (IWB-2500-8)

Required Examination Methods Volumetric EXAMINATION METHOD VOLUMETRIC, SURFACE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 100% of the weld join-ing the surge line to the outlet nozzle would be volumetric-ally examined by the end of the 5-year interval NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval 100% of the weld joining the surge line to the outlet nozzle and of the weld joining the spray line to the nozzle in the upper head would be examined EXTENT OF EXAM FOR INTERNAL ALL WELDS 100%

Remarks Although this item is not re-quired in the code, it is felt that dissimilar metal welds and stainless steel safe ends on the pressurizer should be examined.

REMARKS NONE.

COMMENTS:

EXAMINATION NOW REQUIRES A SURFACE AND INCLUDES ALL DISSIMILAR METAL WELDS ON THE PRESSURIZER, CONSIDERED MORE RESTRICTIVE.

l

TECH SPEC ITEM Item No.

2.5 Category G-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS COMMENTS:

BOLTS 1.875 INCHES IN DIAMETER, THEREFORE NOT APPLICABLE.

Tentative Inspection During 10-Year Interval Not applicable EXTENT OF

. EXAM FOR INTERNAL Remarks There is no bolting 2 inches and larger in diameter on the Surry pressurizer.

REMARKS

TECH SPEC ITEM Item No.

2.6 Category G-2 CODE EQUIVALENT ITEM NO.

B7.20 CATEGORY B-G-2 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED PRESSURIZER BOLTS, STUDS, NUTS Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-1 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% by end of 5-year interval NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(CATEGORY B-G-2 TOTAL)

Tentative Inspection During 10-Year Interval Cumulative 100% by end of interval EXTENT OF EXAM FOR INTERNAL ALL'BOLTING 100%

COMMENTS:

1.

IE BULLETIN 82-02 (NRC) REQUIRES ADDITIONAL SURFACE EXAM WHEN STUDS OR BOLTS REMOVED.

2.

CONSIDERED MORE RESTRICTIVE IN CONJUNCTION WITH I.E.B.

Remarks The bolting below 2 inches in diameter would be visually examined, either in place if the bolted connections is not disas-sembled during the inspection interval, or whenever the bolted connection is disassembled.

The bolting to be examined would include studs and nuts.

REMARKS BOLTING MAY BE EXAMINED:

A) IN PLACE UNDER TENSION:

B) WHEN THE CONNECTION IS DISASSEMBLED; C) WHEN THE BOLTING IS REMOVED.

TECH SPEC ITEM Item No.

2.7 Category H

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Integrally welded vessel supports 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

NOTE 1:

NO INTEGRALLY WELDED ATTACHMENT.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no integrally welded vessel supports on the Surry pressurizer.

REMARKS

TECH SPEC ITEM Item No.

2.8 Category I-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Vessel cladding 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval None NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval 1 patch (36 square inches)

EXTENT OF EXAM FOR INTERNAL COMMENTS:

NO VESSEL CLADDING INSPECTION REQUIRED BY 80W80 CODE, THEREFORE LESS RESTRICTIVE.

Remarks A selected patch of the pressurizer cladding would be visually examined when entry into the vessel is made available for necessary maintenance.

REMARKS

TECH SPEC ITEM Item No.

3.1 Category B

CODE EQUIVALENT ITEM NO.

B2.40 CATEGORY B-B Required Examination Areas Longitudinal and circumferential welds, including tube sheet-to-head or shell welds on the primary side 2ND INTERVAL PARTS EXAMINED TUBESHEET-TO-HEAD

,WELD (FIG. NO.

IWB-2500-6)

Required Examination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 5% of the length of the circumferential weld joining the lower primary head to the tube sheet of one steam generator would be inspected.

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval By the end of the interval, 5% of the length of all of the welds joining the primary heads to the tube sheets would be inspected.

100%

EXTENT OF EXAM FOR INTERNAL ALL WELDS (3 S/G)

COMMENTS:

INCREASED EXAMINATION REQUIREMENTS TO 100% COVERAGE MAKES THIS REQUIREMENT MORE RESTRICTIVE.

Remarks None.

REMARKS NONE.

TECH SPEC ITEM Item No.

3.2 Category D

CODE EQUIVALENT ITEM NO.

CATEGORY B3.130 B-D B3.140 B-D Required Examination Areas Primary nozzle-to-vessel head welds and nozzle-to-head inside radiused section 2ND INTERVAL PARTS EXAMINED STEAM GENERATORS NOZZLE-TO-VESSEL WELDS NOZZLE-TO-INSIDE RADIUS SECTION (FIG. NO. IWB-2500-7d)

Required Examination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 25-50%

REMAINING BY END OF 3RD PERIOD COMMENTS:

EXAMINATION CONSIDERED MORE RESTRICTIVE SINCE NO EXAM PREVIOUSLY REQUIRED.

Tentative Inspection During 10-Year Interval (See remarks)

EXTENT OF EXAM FOR INTERNAL ALL NOZZLES (INCLUDES NOZZLE-TO-VESSEL WELD AND ADJACENT AREAS OF NOZZLE AND VESSEL)

Remarks There are no nozzle-to-head welds in the primary heads of the steam generators as the nozzles are integrally cast with the head.

REMARKS IF EXAMINATIONS ARE CONDUCTED FROM INSIDE THE COMPONENT AND THE NOZZLE WELD IS EXAMINED BY STRAIGHT BEAM ULTRASONIC METHOD FROM THE NOZZLE BORE, THE RE-MAINING SHELL EXAM MAY BE CONDUCTED AT OR NEAR THE END OF THE INTERVAL.

TECH SPEC ITEM Required Required Item Examination Examination No.

Category Areas Methods 3.3 F

Primary nozzle-Visual and to-safe and welds surface and volumetric CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NO.

CATEGORY PARTS EXAMINED METHOD B5.30 B-F STEAM GENERATOR VOLUMETRIC, NOMINAL PIPE SURFACE SIZE )4 IN.

NOZZLE-TO-SAFE END BUTT WELDS (FIG. NO. IWB-2500-8)

COMMENTS:

EXAMINATION NOW REQUIRED, MORE RESTRICTIVE.

TABLE 4.2-'-l Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval (See remarks)

EXTENT OF EXAM FOR INTERNAL 100%

ALL WELDS Remarks The primary nozzles are a but-tered and preparation and the weld is located between the cast nozzle and a cast elbow.

Volumetric inspection is dependent upon meaningful examination techniques.

REMARKS NONE.

TECH SPEC ITEM Item

• No.

3.4 Category G-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS COMMENTS:

BOLTING 1.88 INCHES DIAMETER ( PRIMARY MANWAT), THEREFORE NOT APPLICABLE.

Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There is no pressure-retaining bolting greater than two inches in diameter on the steam generators.

REMARKS

TECH SPEC ITEM Item No.

Category 3.5 G-2 CODE EQUIVALENT ITEM NO.

Bl.30 CATEGORY B-G-2 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED STEAM GENERATORS BOLT, STUDS, NUTS (SURFACE)

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-1 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% by end of 5-year interval NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(CATEGORY B-G-2 TOTAL)

Tentative Inspection During 10-Year Interval Cumulative 100% by end of interval EXTENT OF EXAM FOR INTERNAL ALL BOLTS, STUDS, NUTS (3 S/G)

COMMENTS:

1.

IE BULLETIN 82-02 (NRC) REQUIR,ES ADDITIONAL SURFACE EXAM WHEN BOLTING OR STUDS REMOVED.

2.

CONSIDERED MORE RESTRICTIVE IN CONJUNCTION WITH I.E.B.

Remarks The bolting below 2 inches in diameter would be visually examined, either in place if the bolted connection is not disas-sembled during the inspection interval, or whenever the bolting connection is disas-sembled.

The bolting to be examined would include studs and nuts.

REMARKS BOLTING MAY BE EXAMINED (A) IN PLACE UNDER TENSION:

(B) WHEN THE CONNECTION IS DISASSEMBLED:

(C) WHEN THE BOLTING IS REMOVED.

TECH SPEC ITEM Item No.

3.6 Category H

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Integrally welded vessel supports 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

THERE ARE NO INTEGRALLY WELDED SUPPORTS.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no supports integrally welded to the steam generator pressure boundary.

REMARKS

TECH SPEC ITEM Item No.

3.7 Category I-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Vessel cladding 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval None NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval 1 patch (36 square inches)

EXTENT OF EXAM FOR INTERNAL COMMENTS:

THERE IS NO CORRESPONDING CODE INSPECTION, THEREFORE CONSIDERED LESS RESTRICTIVE.

Remarks A visual examination would be made only such time as the primary side is opened for necessary maintenance.

REMARKS

TECH SPEC ITEM Item No.

4.1 Category F

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Vessel-, pump-,

and valve-safe ends-to-primary pipe welds and safe ends in branch piping welds 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and surface and volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the welds would have been examined EXTENT OF EXAM FOR INTERNAL COMMENTS:

SAFE END EXAMINATIONS ONLY ASSOCIATED WITH REACTOR VESSEL, PRESSURIZER OR STEAM GENERATOR.

Remarks Examination of these welds is covered under Section A, B, and C and explained in the discus-sion.

REMARKS

TECH SPEC ITEM Item No.

4.2 Category J-1 CODE EQUIVALENT ITEM NO.

B9.10 B9.ll B9.12 B9.31 CATEGORY B-J Required Examination Areas Circumferential and longitudinal pipe 'welds and branch pipe connection welds larger than 4 inches in diameter 2ND INTERVAL PARTS EXAMINED NOMINAL PIPE SIZE ~4 IN.

CIRCUMFERENTIAL WELDS LONGITUDINAL WELDS (FIG. NO.

IWB-2500-8)

BRANCH PIPE CONNECTION WELDS

~4 IN.

Required Examination Methods Visual and volumetric EXAMINATION METHOD SURFACE AND VOLUMETRIC COMMENTS:

1.

SURRY CURRENTLY USES 74S75 OPTION.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interva:).

5% of the circumferen-tial welds, including one foot of any longi-tudinal weld on either side of the butt weld, would be examined NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(OF EXTENT)

2.

ADDITIONAL SURFACE REQUIREMENT, THEREFORE.MORE RESTRICTIVE.

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 25% of the circumferen-tial welds in the piping system would have been examined, including one foot of any longitudinal weld on either side of the butt welds EXTENT OF EXAM FOR INTERNAL 80W80 UTILIZES SELECTION PROCESS BASED ON STRESS, MATERIAL AND LOCATION.

100% OF SELECTED CIRCUMFERENTIAL WELDS AND AT LEAST A PIPE DIAMETER LENGTH BUT NOT MORE THAN 12 INCHES OF SELECTED LONGITUDINAL WELDS AT THE CIRCUM-FERENTIAL WELD INTER-SECTION Remarks None.

REMARKS 10CFR 50.55a REQUIREMENTS ALLOWS USE OF 74S75 CODE FOR EXTENT OF EXAMINATION AND EXEMPTIONS.

TECH SPEC ITEM Item No.

Category 4.3 G-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

THERE IS NO BOLTING GREATER THAN 2 INCHES ON PIPING.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There is no bolting 2 inches and larger in the piping system.

REMARKS

TECH SPEC ITEM Item No.

4.4 Category G-2 CODE EQUIVALENT ITEM NO.

B7.50 CATEGORY B-G-2 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED PIPING BOLTS, STUDS, NUTS (SURFACE)

COMMENTS:

REMAINS ESSENTIALLY THE SAME.

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-1 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the bolting would be examined NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(OF B-G-2 CATEGORY)

Tentative Inspection During 10-Year Interval By the end of the interval, 100% of the bolting would be examined 100%

EXTENT OF EXAM FOR INTERNAL ALL BOLTS, STUDS, AND NUTS Remarks All bolting is below 2 inches in diameter and would be visually examined, either in place if the bolted connection is not disas-sembled during the inspection interval, or whenever the bolted connection is disassembled.

The bolting to be examined would include studs and nuts.

REMARKS BOLTING MAY BE EXAMINED:

(A) IN PLACE UNDER TENSION (B) WHEN THE CONNECTION IS DISASSEMBLED (C) WHEN BOLTING IS REMOVED.

TECH SPEC ITEM Item No.

4.5 Category K-1 CODE EQUIVALENT ITEM NO.

Bl0.10 CATEGORY B-K-1 Required Examination Areas Integrally welded supports 2ND INTERVAL PARTS EXAMINED PIPING INTEGRALLY WELDED ATTACHMENTS (FIG. NO. 2500-13, 14 and 15)

Required Examination Methods Visual and surface EXAMINATION METHOD VOLUMETRIC OR SURFACE AS APPLICABLE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 10% of supports would be examined NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(OF SELECTION)

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 25% of the supports would be examined EXTENT OF EXAM FOR INTERNAL EXAMINATION INCLUDES ALL WELDED ATTACHMENTS OF PIPING SELECTED FOR EXAM IN CATEGORY B-J Remarks Areas subject to examination would include any integrally welded external support attachment *which includes the welds to the pressure containing boundary, the base metal beneath the weld zone, and along the support attachment for distance of two base metal thicknesses.

REMARKS INCLUDES THOSE ATTACHMENTS WHOSE ATTACHMENT BASE MATERIAL DESIGN THICKNESS IS 5/8 INCH AND GREATER ONLY.

INSPECTION ENDS AFTER 2ND INTERVAL.

COMMENTS:

1.

BASE MATERIAL LIMITATION LESS RESTRICTIVE, USE OF VOLUMETRIC, WHEN APPLICABLE, MORE RESTRICTIVE, HOWEVER ALSO OPTIONAL.

2.

INSPECTION ENDS AFTER SECOND INTERVAL, LESS RESTRICTIVE.

TECH SPEC ITEM Item No.

4.6 Category K-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Piping support and hanger 2ND INTERVAL PARTS EXAMINED SUPPORT PROGRAM UNDER DEVELOPMENT WILL USE THE REQUIREMENTS OF CATEGORY FA, FB, AND FC OF THE 80W81 CODE Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-3, VT-4 AS APPLICABLE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the supports would be examined NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the supports would be examined EXTENT OF EXAM FOR INTERNAL PERIOD AND INTERVAL REQUIREMENTS WILL CORRESPOND TO THE REQUIREMENTS OF IWB, IWC AND IWD FOR THE COMPONENT/PIPING THAT THE SUPPORT IS ATTACHED TO COMMENTS:

1.

PRIOR TO PROGRAM IMPLEMENTATION RULES OF 74S75 B-K-2 REQUIRED.

2.

FREQUENCY CURRENTLY USES A THIRD PER PERIOD OF ALL SUPPORTS.

Remarks The support members and struc-tures subject to examination would include those supports within the system whose structural integrity is relied upon to withstand the design loads and seismic-induced displacements.

REMARKS AS REQUIRED BY IWF OF ASME SECTION XI USE OF MULTIPLE COMPONENT DESIGNATION ALLOWED, LIMITING EXAM TO ONE TRAIN.

3.

EVENTUAL IWF 80W81 WILL PROVIDE A MORE COMPREHENSIVE EXAMINATION, MORE RESTRICTIVE, BUT LESS SUPPORTS SELECTED, LESS RESTRICTIVE

• TECH SPEC ITEM Item No.

4.7 Category J-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Circumferential and longitudinal pipe welds and branch pipe connections 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 50% of the welds would be examined NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval By the end of the inspection interval a cumulative 100% of the welds and pipe branch connections would be examined.

EXTENT OF EXAM FOR INTERNAL COMMENTS:

NO CORRESPONDING EXAMINATION IN CURRENT CODE 80W80 UNLESS REFERENCING B-P PRESSURE TEST.

Remarks REMARKS

TECH SPEC ITEM Item No.

4.8 Category J-1 CODE EQUIVALENT ITEM NO.

B9.32 B9.40 CATEGORY B-J Required Examination Areas Socket welds and pipe branch connections welds 4 inches in diameter and smaller 2ND INTERVAL PARTS EXAMINED NOMINAL PIPE SIZE

<4 IN.

(FIG. NO. IWB-2500-9, 10, 11)

SOCKET WELDS (FIG. NO. IWB-2500-8)

Required Examination Methods Visual and surface EXAMINATION METHOD SURFACE SURFACE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 5% of the circumferen-tial welds and 5% of the pipe branch con-

• nection welded joints would be examined NORMAL PERIOD REQUIREMENTS Tentative Inspect.ion During 10-Year Interval By the end of the inspection interval, a cumulative 25% of the circumferential welds in the piping system and 25% of the pipe branch connections welded joints would be examined EXTENT OF EXAM FOR INTERNAL SELECTION REQUIREMENTS SIMILAR TO LARGER B-J PIPING.

Remarks REMARKS COMMENTS:

SELECTION CURRENTLY USES 74S75 REQUIREMENTS WHICH IS ESSENTIALLY THE SAME.

USE OF 80W80 EXTENT OF EXAMINATION LESS RESTRICTIVE.

TECH SPEC ITEM Item No.

Category 5.1 L-1 CODE EQUIVALENT ITEM NO.

Bl2.10 CATEGORY B-L-1 Required Examination Areas Pump casing welds 2ND INTERVAL PARTS EXAMINED PUMP CASING WELDS Required Examination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC COMMENTS:

1.

RADIOGRAPHY CONDUCTED THE FIRST INTERVAL.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval None N/A NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval None EXTENT OF EXAM FOR INTERNAL 1 PUMP, DEFERRAL TO END OF INTERVAL PERMISSIBLE Remarks The only feasible method known to date to volumetrically inspect these pump weld casings is radiography.

It is not known if such radiography can be performed in service due to the design and the radiation level in the component.

If experience or a study indicates such radiography is possible, the inspection would be performed at the frequency specified in the Code.

In any case, a visual inspection would be made at such time as the pump is opened for any purpose.

REMARKS NONE.

2.

RELIEF MAY BE REQUESTED IN THE FUTURE FROM VOLUMETRIC EXAMINATION DUE TO NO DOCUMENTED EVIDENCE OF ANY PROBLEM IN INDUSTRY AND BECAUSE OF THE RADIATION EXPOSURE.

THIS WILL BE A SEPARATE RELIEF IF SUBMITTED.

3.

CURRENT CODE MORE RESTRICTIVE REQUIRING VOLUMETRIC EXAM.

TECH SPEC ITEM Item No.

5.2 Category L-2 CODE EQUIVALENT ITEM NO.

CATEGORY Bl2.20 B-L-2 Required Examination Areas Pump casings 2ND INTERVAL PARTS EXAMINED PUMP CASING (INTERNAL SURFACES)

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-3 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval None NORMAL PERIOD REQUIREMENTS N/A Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the available inner surfaces of the required pumps would be examined if the pumps are disassembled for maintenance EXTENT OF EXAM FOR INTERNAL EXAMINATION WOULD BE CONDUCTED IN CONJUNC-TION WITH REQUIRED VOLUMETRIC EXAM.

COMMENTS:

1.

RELIEF MAY BE REQUESTED TO LIMIT THIS EXAMINATION TO COINCIDE WITH MAINTENANCE DISASSEMBLY.

Remarks The only pumps involved in this program are the coolant pumps.

REMARKS NONE.

2.

CURRENTLY, CODE 80W80 MORE RESTRICTIVE BECAUSE OF REQUIRED INSPECTION; ACTIVATION OF RELIEF WOULD ESSENTIALLY CAUSE ITEM TO REMAIN THE SAME.

TECH SPEC ITEM Item No.

5.3

• Category F

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Nozzle-to-safe end welds 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

THERE ARE NO NOZZLE-TO-SAFE END WELDS ON THE PUMPS.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not Applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not Applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no nozzle-to-safe end welds on the pumps.

REMARKS

TECH SPEC ITEM Item No.

5.4 Category G-1 CODE EQUIVALENT ITEM NO.

B6.180 B6.190 B6.200 CATEGORY B-G-1 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED BOLTS AND STUDS (FIG. NO, IWB-2500-12)

FLANGE SURFACE, WHEN CONNECTION DISASSEMBLED (SURFACES, INCLUDING 1 IN.

ANNULAR SURFACE OF FLANGE SURROUNDS EACH STUD)

NUTS, BUSHINGS, WASHERS (SURFACES)

Required Examination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

COMMENTS:

1,

2.

I.E. BULLETIN 82-02 REQUIRES SURFACE EXAM ON BOLTS OR STUDS WHEN REMOVED.

SURFACE REQUIREMENT OF I.E. BULLETIN MAKES THIS MORE RESTRICTIVE.

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the bolting would be examined EXTENT OF EXAM FOR INTERNAL ALL BOLTS, STUDS, NUTS, BUSHINGS, THREADS IN FLANGE STUD HOLES Remarks Bolting 2 inches and larger in diameter would be examined either in place under tension, or when the bolting is removed or when the bolting connection is disassembled for maintenance purposes.

The bolting and areas to be examined would include the studs, nuts, bushings, threads in the base material, and the flange ligaments between threaded stud holes.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL PERMISSIBLE.

BOLTING MAY BE EXAMINED:

(A) IN PLACE UNDER TENSION:

(B) WHEN THE CONNECTION IS DISASSEMBLED:

(C) WHEN BOLTING IS REMOVED.

TECH SPEC ITEM Item

, No.

5.5 Category G-2 CODE EQUIVALENT ITEM NO.

B7.60 CATEGORY B-G-2 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED BOLTS, STUDS, NUTS (SURFACE)

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-1 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(CATEGORY B-G-2.

TOTAL)

GCJMMENTS:

1.

IE BULLETIN 82-02 REQUIRES SURFACE EXAM ON BOLTS OR STUDS.

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the bolting would be examined EXTENT OF EXAM FOR INTERNAL ALL BOLTS, STUDS, AND NUTS

2.

REQUIRED EXAMINATION AND SURFACE REQUIREMENT (IEB 82-02) MAKES THIS MORE RESTRICTIVE.

Remarks Bolting below 2 inches in diameter would be visually examined, whenever the bolted connection is disassembled for maintenance purposes. *The bolting to be examined would include studs and nuts.

REMARKS BOLTING MAY BE EXAMINED:

(A) IN PLACE UNDER TENSION, (B) WHEN THE CONNECTION IS DISASSEMBLED (C) WHEN BOLTING IS REMOVED.

TECH SPEC ITEM Item No.

5.6 Category K-1 CODE EQUIVALENT ITEM NO.

Bl0.10 CATEGORY B-K-1 Required Examination Areas Integrally welded supports 2ND INTERVAL PARTS EXAMINED PUMPS INTEGRALLY WELDED ATTACHMENTS (FIG. NO. 2500-13, 14, 15)

Required Examination Methods Visual and volumetric EXAMINATION METHOD VOLUMETRIC OR SURFACE AS APPLICABLE TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 10% of the supports would be visually examined NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 25% of the supports would be visually examined EXTENT OF EXAM FOR INTERNAL 100% WELDED ATTACHMENTS WHERE BASE MATERIAL DESIGN THICKNESS IS 5/8 IN. AND GREATER COMMENTS:

1.

SURFACE REQUIREMENT COULD BE LESS RESTRICTIVE, NO INSPECTION AFTER 2ND INTERVAL, LESS RESTRICTIVE.

2.

BASE MATERIAL REQUIREMENT, LESS RESTRICTIVE.

Remarks None.

REMARKS INSPECTION ENDS AFTER SECOND INTERVAL.

TECH SPEC ITEM Item No.

5.7 Category K-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Supports and hangers 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the supports would be examined NORMAL PERIOD REQUIREMENTS COMMENTS:

COMMENTS OF SUPPORT PROGRAM ITEM 4.6 REMAIN THE SAME FOR THIS ITEM.

Tentative Inspection During 10-Year Interval Cumulative 100% of the supports would be examined EXTENT OF EXAM FOR INTERNAL Remarks None.

REMARKS

TECH SPEC ITEM Item No.

6.1 Category H-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Valve body welds 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS COMMENTS:

ALL VALVES STILL SUBJECT TO THIS INSPECTION ARE CAST VALVES.

Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks All the valves subject to this inspection are cast valves, thus this item is not applicable.

REMARKS

TECH SPEC ITEM Item No.

5.8 Category CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Primary pump Flywheel 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and Volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS COMMENTS:

1.

NO CORRESPONDING CODE 80W80 EXAM, LESS RESTRICITVE.

Tentative Inspection During 10-Year Interval 100% examination at or near the end.of the inspection interval EXTENT OF EXAM FOR INTERNAL Remarks All flywheels shall be visually examined at the first refueling

• and third refueling.

Every three (3) years an in-place ultrasonic volumetric examina-tion of the areas of higher stress concentration at the bore and keyway of each flywheel shall be performed.

At the end of every 10 years, all flywheels*

will be subject to a 100%

ultrasonic inspection.

REMARKS

2.

TECHNICAL SPECIFICATION CHANGE ENDORSES INSPECTION PER REGULATORY POSITION C.4.B. OF REG. GUIDE 1.14 REV. 1, AUGUST 1975, MORE RESTRICTIVE

• TECH SPEC ITEM Item No.

6.2 Category H-2 CODE EQUIVALENT ITEM NO.

Bl2.40 CATEGORY B-M-2 Required Examination Areas Valve bodies 2ND* INTERVAL PARTS EXAMINED VALVE BODY EXCEED-ING 4 IN.

NOMINAL PIPE SIZE (INTERNAL SUR-FACES)

Required Examination Methods Visual EXAMINATION METHOD VISUAL, VT-3 TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

• 2ND: 50-67%

3RD: 100%

Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the available inner surfaces of the required valves would be examined EXTENT OF EXAM FOR INTERNAL 100%

INTERNAL SURFACE, LIMITED TO ONE VALVE WITHIN EACH GROUP OF VALVES THAT ARE OF THE SAME CONSTRUCTIONAL DESIGN, MANUFACTURING METHOD AND FUNCTION (SIMILAR)

Remarks The valves subject to this in-spection may be examined during maintenance or at the end of each interval.

REMARKS DEFERRAL OF INSPECTION TO END OF INTERVAL, PERMISSIBLE.

COMMENTS:

1.

RELIEF GRANTED TO ONLY INSPECT VALVES DURING MAINTENANCE DISASSEMBLY ONLY.

AUGMENTED THICKNESS MEASUREMENT (VALVE BODY) REQUIRED.

2.

LESS RESTRICTIVE DUE TO MAINTF.NANCE DEFERRAL.

TECH SPEC ITEM Item No.

Category 6.3 F

CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Valve-to-safe and welds 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

NO DISSIMILAR METAL WELDS IN.THIS CATEGORY.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no valves in this system with dissimilar metal welds.

REMARKS

TECH SPEC ITEM Item No.

6.4 Category G-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD TABLE 4,2-1 Extent of Examination Planned During First 5-Year Interval (See remarks)

NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the bolting 2 inches and larger would be examined EXTENT OF EXAM FOR INTERNAL Remarks Bolting 2 inches and larger in diameter would be examined either in place under tension or when the bolting is removed or when the bolting connections is disassembled for maintenance purposes.

The bolting in areas to be examined would include the studs, nuts, bushings, threads in the flange ligaments between threaded stud holes.

REMARKS COMMENTS:

NO VALVES ARE IN CATEGORY B-M-1, THEREFORE NO BOLTING IS REQUIRED TO BE EXAMINEP IN B-G-1, LESS RESTRICTIVE,

TECH SPEC ITEM Item No.

6.5 Category G-2 CODE EQUIVALENT ITEM NO.

B7.70 CATEGORY B-G-2 Required Examination Areas Pressure retain-ing bolting 2ND INTERVAL PARTS EXAMINED VALVE BOLTS, STUDS, NUTS (SURFACE)

Required Examination Methods Visual and volumetric EXAMINATION METHOD VISUAL, VT-1 COMMENTS:

EXAMINATION REMAINS ESSENTIALLY THE SAME

• TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33%

NORMAL PERIOD REQUIREMENTS 1ST: 16-34%

2ND: 50-67%

3RD: 100%

(OF B-G-2)

Tentative Inspection During 10-Year Interval By the end of the interval, cumulative 100% of the bolting would be examined EXTENT OF EXAM FOR INTERNAL ALL BOLTS, STUDS, AND NUTS Remarks All bolting is below 2 inches in diameter and would be visually examined, either in place if the bolting connection is not disassembled at the inspection interval, or whene_ver the bolting connection is disassembled.

The bolting to be examined would include studs and nuts.

REMARKS BOLTING MAY BE EXAMINED:

(A) IN PLACE UNDER TENSION, (B) WHEN THE CONNECTION IS DISASSEMBLED, (C) WHEN THE BOLTING IS REMOVED.

TECH SPEC ITEM Item No.

6.6 Category K-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Integrally welded supports 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD COMMENTS:

NO INTEGRALLY WELDED SUPPORTS ON THE VALVES.

TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Not applicable NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks There are no integrally-welded supports on the valves subject to this examination.

REMARKS

L' TECH SPEC ITEM Item No.

6.7 Category K-2 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Supports and hangers 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval 33% of the supports and hangers would be examined NORMAL PERIOD REQUIREMENTS COMMENTS:

COMMENTS ON THE SUPPORT PROGRAM IN ITEM.4.6 REMAIN THE SAME FOR THIS ITEM

• Tentative Inspection During 10-Year Interval By the end of the interval, a cumulative 100% of the supports and hangers would be examined EXTENT OF EXAM FOR INTERNAL Remarks The support members and struc-tures subject to examination would include those supports for piping, valves, and pumps within the system boundary, whose structural integrity is relied upon to withstand the design loads and seismic-induced displacements.

The support settings of constant and variable spring-type han-gers, snubbers and shock absorb-ers would be inspected to verify proper distribution of design loads among the associated sup-port components.

REMARKS

TECH SPEC ITEM Item No.

7.1 Category CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Materials Irradiation Surveillance 2ND INTERVAL PARTS EXAMINED COMMENTS:

NOT CHANGED, REMAINS ON TABLE 4.2-1.

Required Examination Methods Tensile and Charpy V notch (wedge open loading) and Dosimetry EXAMINATION METHOD TABLE 4.2-1 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.

NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Capsules shall be removed and examined after 10 years EXTENT OF EXAM FOR INTERNAL Remarks Capsule 4 shall be removed and examined after 20 years.

Capsules 5-8 are extra capsules for complementary or duplicate testing.

REMARKS

TECH SPEC ITEM Item No.

7.2 Category CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Low Head SIS Piping located in valve pit 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval (See Remarks)

NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks This pipe shall be visually inspected at each refueling shutdown.

REMARKS COMMENTS:

WILL BE COVERED BY CLASS 2, SYSTEM PRESSURE TESTS AND CORRESPONDING VT-2 EXAMINATION, ESSENTIALLY REMAINS THE SAME.

TECH SPEC ITEM Item No.

7.3 Category CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Low pressure turbine rotor 2ND INTERVAL PARTS EXAMINED COMMENTS:

WILL PUT BACK IN.

Required Examination Methods Visual and magnet part-icle or dye penetrant EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First' 5-Year Interval 100% of blades NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Not applicable EXTENT OF EXAM FOR INTERNAL Remarks REMARKS

(

TECH SPEC ITEM Item No.

8.1.1 8.1.2 8.1.3 Category J-1 J-2 J-1 CODE EQUIVALENT ITEM NO.

CATEGORY Required Examination Areas Circumferential and longitudinal pipe welds and branch pipe connections larger than 4 inches in diameter Circumferential and longitudinal pipe welds and branch pipe connections Socket welds and pipe branch connections welds 4 inches in diameter and smaller 2ND INTERVAL PARTS EXAMINED Required Examination Methods Visual and volumetric EXAMINATION METHOD TABLE 4.2-1 Extent of Examination Planned During First 5-Year Interval Three times the extent of Section D.

Item No. 4.2 of Table 4.2-1 Three times the extent* of Section D, Item No. 4.7 of Table 4.2-1 Three times the extent* of Section D, Item No. 4.8. of Table 4.2-1 NORMAL PERIOD REQUIREMENTS Tentative Inspection During 10-Year Interval Three time the extent of Section D, Item No. 4.2 of Table 4.2-1 Three times the extent of Section D, Item No.

4.7 of Table 4.2-1 Three times the extent of Section D, Item No.

4.7 of Table 4.2-1 EXTENT OF EXAM FOR INTERNAL Remarks

• Extent in this context is interpreted to mean that inspections will be conducted at three times the inspection frequency required by Items 4.2, 4.7 and 4.8 of Table 4.2-1.

Thus, those examinations planned for the first five year interval for Items 4.2, 4.7 and 4.8 will be performed every 1-2/3 years (generally each normal refueling outage).

See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7,

§10).

Same as above.

REMARKS NOTE:

THESE REQUIREMENTS WILL BE MAINTAINED, HOWEVER, REWRITTEN DUE TO REFERENCED SECTIONS BEING DELETED.

(ESSENTIALLY THE SAME)

ITEMS 8.2.1 AND 8.2.2 WILL BE MAINTAINED IN TOTAL, HOWEVER RENUMBERED.

(ESSENTIALLY THE SAME)

JDH:mdl/ISI/001

' I.

I Page TS 4.3-1 (Specification 4.3) "ASME Code Class 1, 2, and 3 System Pressure Tests".

Specification modified to incorporate standard reference to ASME Section XI requirements for inservice inspection of Class 1, 2, and 3 components.

Augmented leakage test requirements have been restated.

Deletion of new strength weld _ inspection requirements made because specification covered in T.S.

4.0.3 repair/replacement program.

(More restrictive than present Technical Specifications.)

Page TS 4.5-1 (Specification 4.5) "Spray Systems Tests".

Specification modified to reference ASME Code Section XI for operability tes_ting, as follows:

A.

(1)

Containment spray pumps tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(2)

Inside containment recirculation _spray pumps tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(3)

Outside containment recirculation spray pumps tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(4)

Weighted loaded check valves in containment tested per ASME.

Section XI.

(Essentially the same frequency, less restrictive test options.)

(5)

All MOVs in containment spray or recirculation spray flow path tested. per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(6)

Unchanged.

(7)

Spray nozzles in the refueling water storage tank shall be functionally checked while performing the containment spray pump test.

(Less restrictive frequency.)

Test waiver deleted because waiver_ of tests during shutdown periods is covered by ASME Section XI.

B.

(1)

Acceptance criteria references ASME Section XI for the inside recirculation spray pumps.

(Essentially the same as amp test referenced per relief request from ASME Section XI.)

(2)

Acceptance criteria references ASME Section XI for the contain-ment* spray pumps.

(More restrictive than present Technical Specifications.)

(3)

Acceptance criteria reference ASME Section XI for weight loaded check valves.

(More restrictive than present Technical Specifi-cations.)

(4)

Acceptance criteria references ASME Section XI for motor oper-ated valves.

(More restrictive than present Technical Specifi-cations.)

(5)

Unchanged.

(6)

Unchanged.

(7)

Acceptance criteria references ASME Section XI for the outside recirculation spray pumps.

(More restrictive than present Technical Specifications.)

NOTE:

Bases slightly modified to infer code pump testing and frequency requirements.

(Essentially the same.)

Page TS 4.7-1 (Specification 4.7)

"Main Steam Line Trip Valves".

Deletion of partial closure test required due to difficulty in control-ling partial closure.

Substituted full closure test more conservative.

Acceptance criteria references ASME Section XI for valve testing.

(More restrictive than present Technical Specifications.)

Page TS

4. 8-1 (Specification

4. 8)

"Auxiliary Feedwater System".

Specification modified to reference ASME Code Section XI for operability testing, as follows:

A.

(1)

Motor-driven auxiliary steam generator feedwater pump tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

B.

(2)

Turbine-driven auxiliary steam generator feedwater pump tested.

per ASME Section XI..

(Less restrictive frequency, more restrictive test criteria.)

(3)

Auxiliary steam generator feedwater pump discharge valves tested for ASME Section XI.

(Less restrictive frequency, more restric-tive test criteria.)

(4a) Unchanged.

(4b) Unchanged.

(5)

Parameters changed to apply when only one reactor is shutdown.

(Specification 4.8.A.6 added to apply when both reactors are shutdown.)

(Sa) Auxiliary steam generator feedwater pumps tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(Sb) Auxiliary steam generator feedwater pump cross-connect valves tested per ASME Section XI.

(Less restrictive frequency, more restrictive test criteria.)

(6)

Add provision for waiving test requirements of ASME Section XI during periods of extended shutdown of both units.

(Less restrictive frequency.)

Acceptance criteria Specification 4.8.A.

Specifications.)

references ASME Section XI for (More restrictive than present tests in Technical

I L

• ,* (

.... ~

Page TS 4.11-1 (Specification 4.11) "Safety Injection System Tests".

System test now allows administrative control of charging and safety injection pumps.

(Remains essentially the same.)

Pump and valve testing are conducted in accordance with ASME Section XI.

(Frequency less restrictive, test requirements more restrictive.* )

Acceptance criteria for system test remains essentially unchanged.

Pump and valve acceptance criteria references ASME Section XI.

(More restrictive.)

The proposed change; to Technical Specifications have been reviewed and it is concluded that:

(a) The probability of occurrence or the consequence of an accident or malfunction of equipment important to safety and previously evaluated in the Safety Analysis Report is not increased since the systems are still proven to be operational by functional test in accordance with ASME Section XI.

(b) The potential for an accident or malfunction of a different type than previously evaluated in the Safety Analysis Report is not created.

The level of integrity and the function of these systems are functional tested as prescribed by ASME Section XI.

(c) The required margin of safety on the basis of the Technical Speci-ficat..ion is not reduced because the system is proven operable by*

standards set up in ASME Section XI Codes.

Therefore, this request does not pose an unreviewed safety question as defined in 10CFR50. 59.

The proposed change does not pose a significant hazards consideration as defined in 10CFR50. 92.

The Commission has provided examples of changes that constitute "no significant hazards" consideration in the Federal Register, Volume 48, page 14870.

Example (vii) consists of a change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keeping with the regulations.

The proposed change is similar to example (vii) in that, the inservice inspection, repair, and replacement of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves are being revised to conform to Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g).