ML18143B449

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Proposed Tech Specs,Updating Inservice Insp Proposal in Response to NRC 850528 Request for Addl Info
ML18143B449
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/30/1985
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18143B448 List:
References
NUDOCS 8509100238
Download: ML18143B449 (97)


Text

ATTACHMENT 1 TECHNICAL SPECIFICATION CHANGES FOR INSERVICE INSPECTION AND TESTING SURRY POWER STATION UNITS 1 AND 2

    • 8509100238 850830 PDR ADOCK 05000280

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

TS 4.0-1 4.0 SURVEILLANCE REQUIREMENTS

  • 4.0.1 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.

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

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

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:

TS 4.0-2 ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing Inservice Inspection and Inservice Inspection Testing Activities and Testing Activities Monthly At least once per 31 days Quarterly or Every 3 Months At least once per 92 days Cold Shut Down At least once per CSD Refueling Shut Down At least once per RSD Inspection Period Per Table - IWB, IWC-2412-1 Inspection Interval 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 hours before being declared inoperable .

  • TABLE 4.1-2A MINIMUM FREQUENCY FOR EQUIPMENT TESTS FSAR Section Description Test Frequency Reference
1. Control Rod Assemblies Rod drop times of all Each refueling shutdown or after 7 full length rods at disassembly or maintenance hot conditions requiring the breach of the Reactor Coolant System integrity
2. Control Rod Assemblies Partial movement of Every 2 weeks 7 all rods
3. Refueling Water Chemical Functional Each refueling shutdown 6 Addition Tank
4. Pressurizer Safety Valves Setpoint Per TS 4.0.3 4
5. Main Steam Safety Valves Setpoint Per TS 4.0.3 10
6. Containment Isolation Trip *Functional Each refueling shutdown 5
7. Refueling System Interlocks *Functional Prior to refueling 9.12
8. Service Water System *Functional Each refueling shutdown 9.9
9. Fire Protection Pump and Functional Monthly 9.10 Power Supply
10. Primary System Leakage *Evaluate Daily 4
11. Diesel Fuel Supply *Fuel Inventory 5 days/week 8.5 1-3 Ul
12. Boric Acid Piping Heat *Operational Monthly 9.1 .p-.

Tracing Circuits I-'

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13. Main Steam Line Trip Functional 10 '° t;d (1) Full closure (1) Before each startup

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

1. From C.S. Pump CS-P-lA to M.O. 15 minutes Monthly Run separately or run in Isolation Valves conjunction with or immediately after pump test required by Specification 4.5.A.l
2. From C.S. Pump CS-P-lB to M.O. 20 minutes Monthly Run separately or run in Isolation Valves conjunction with or immediately after pump test required by Specification 4.5.A.l
3. From L.H.S.I. Pump, SI-P-lA, 20 minutes Monthly Run separately or run in Discharge Line to MOV 863A conjunction with or immediately after pump test required by Specification 4.11.B.1
4. S.I. line, from charging pump discharge Flushes to be performed only loop fill header to containment missile when R.C. System pressure is barrier, for flow to: > 1500 psig.
a. R.C. hot leg loop 1 15 minutes Monthly
b. R.C. hot leg loop 2 10 minutes Monthly
c. R.C. hot leg loop 3 15 minul;es Monthly
5. S.I. line, from charging pump discharge Flushes to be performed only header to containment missile barrier, when R.C. System pressure is for flow to: > 1500 psig.

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a. R.C. cold leg loop 1 5 minutes Monthly +:-
b. R.C. cold leg loop 2 5 minutes Monthly f--'
c. R.C. cold leg loop 3 5 minutes Monthly I f---1 f--'

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

1. From C.S. Pump 2-CS-P-lA 20 minutes Monthly Run separately or run in to M.O. Isolation Valves conjunction with or immediately after pump test required by Specification 4.5.A.l
2. From C.S. Pump 2-CS-P-lB 15 minutes Monthly Run separately or run in to M.O. Isolation Valves conjunction with or immediately after pump test required by Specification 4.5.A.l
3. From L.H.S.I. Pump, 2-SI-P-lA, 20 minutes Monthly Run separately or run in Discharge Line to MOV 2-863A conjunction with or immediately after pump test required by Specification 4.11.B.1
4. 6" S.I. line, from L.H.S.I. pumps to Flushes to be performed only containment missile barrier, for flow when R.C. System pressure is to: > 1500 psig. Run separately or run in conjunction with or
a. R.C. hot leg loop 1 35 minutes Monthly immediately after pump test
b. R.C. hot leg loop 2 35 minutes Monthly required by Specification
c. R.C. hot leg loop 3 35 minutes Monthly 4.11.B.1
5. S.I. line, from charging pump discharge Flushes to be performed only header to containment missile barrier, when R.C. System pressure is for flow to: > 1500 psig.
a. R.C. cold leg loop 1 5 minutes Monthly
b. R.C. cold leg loop 2 5 minutes Monthly 1--'
c. R.C. cold leg loop 3 5 minutes Monthly *I 1--'

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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.

tions in this requirement.

section, Certain components, under Miscellaneous Inspec-were added because of no corresponding This added requirement provides the inspection necessary to code 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 TABLE.

Required Required Item Examination Examination Tentative Inspection No. Area Methods During 10-Year Interval Remarks 1.1 Materials Tensile and Capsules shall be removed Capsule #1 = First Irradiation Charpy V notch and examined after 10 refueling Surveillance (wedge open years. (See Notes 1 and 2) loading) and Capsule #2 = At five dosimetry as years necessary to insure surveil- Capsule 113 = At 10 lance. years Capsule 114 = At 20 years Capsule tlS-8 = Are spares for complemen-tary or duplicate testing.

Note 1: 1 year corresponds to 1 year effective full power operation.

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 TABLE Required Required Item Examination Examination Tentative Inspection No. Area Methods During 10-Year Interval Remarks 1.2 Primary Pump See remarks See remarks Examination to be con-Flywheel ducted in accordance with regulatory position C. 4. b of regulatory guide 1.14 Rev.I, August 1975.

1.3 Low Pressure Visual and 100% of blades every None.

Turbine Rotor Magnetic 5 years Particle or Dye Penetrant SECTION B. SENSITIZED STAINLESS STEEL 2.1.1 Circumferential Visual and By the end of the A minimum of 5% of the and longitudinal Volumetric interval, a cumulative welds will be examined pipe welds and 75% of the circumferen- every 1-2/3 years branch pipe tial welds in the piping (generally each normal connections system would have been refueling outage).

larger than 4 examined, including one See Transcript of inches in foot on any longitudinal Hearing (pp. 303-304) diameter. weld on either side of and Initial Decision the butt welds. (p. 7, p. 10) .

2.1.2 Circumferential Visual By the end of the A minimum of 50% of and longitudinal interval a cumulative the welds will be pipe welds and 100% of the welds and examined every 1-2/3 branch pipe pipe branch connections years (generally, each connections. would be examined a normal refueling outage) minimum of three times. See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7, p. 10).

SECTION B. SENSITIZED STAINLESS STEEL TABLE Required Required Item Examination Examination Tentative Inspection No. Area Methods During 10-Year Interval Remarks 2.1.3 Socket welds Visual and By the end of the interval, A minimum of 5% of the and pipe branch Surface a cumulative 75% of the circumferential welds connections circumferential welds in and 5% of the pipe welds 4 inches the piping system and 75% branch connection in diameter of the pipe branch connec- welded joints will be and smaller tions welded joints would examined every 1-2/3 be examined. years (generally each normal refueling outage). See Transcript of Hearing (pp. 303-304) and Initial Decision (p. 7, p. 10).

2.2.1 Containment and Visual and (See Remarks) At least 25 percent of Recirculation Surface 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)

Required Required Item Examination Examination Tentative Inspection No. Area Methods During 10-Year Interval Remarks 2.2.2 Remaining Visual and (See Remarks) The piping would be in-sensitized Surface spected every two years.

stainless The inspection will in-steel piping 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

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.

BASIS 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

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

Specification A. Tests and Frequencies

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

B. 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.

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

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.

B. 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.

TS 4 .11-2 B. 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.

Basis

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

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

passive safeguard. In accordance with The accumulators are a Specification 4.1, the water volume and pressure in the accumulators are checked periodically.

REFERENCE FSAR Section 6.2, Safety Injection System

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) Main steam safety valves tested to code frequency.

(Less restrictive than present Technical Specifi-cations.)

Table 4.1-2A (5) Pressurizer safety valves tested to code frequency.

(Less restrictive than present Technical Specifi-cation.)

Table 4.l-2A (13) 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.)

Table 4.l-3A (1), Remarks changed to accommodate quarterly testing (2), (3) and allowed by code for listed pumps. Flushing will Table 4.l-3B, C. still be required monthly. (Essentially the same.)

      • (2), (3), and (4)

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:

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.1 A Longitudinal and Volumetric 0% 5% of the length of the The required examinations may be circumferential circumferential welds; made at or near the end of the shell welds in 10% of the length of the 10-year inspection interval.

core region longitudinal welds When the longitudinal and cir-cumferential weld have received an exposure to y utron fluence in excess of 10 9 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl.10 BA SHELL WELDS VOLUMETRIC 1ST: 16-34% 100% OF WELD LENGTH DEFERRAL OF INSPECTION TO END OF Bl.11 CIRCUMFERENTIAL INTERVAL PERMISSIBLE.

Bl.12 LONGITUDINAL (ONE BELTLINE REGION WELD EACH)

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

ANY.) (FIG. NO.

IWB2500-l,2) 18 COMMENTS: 1. CURRENT NEUTRON FLUENCE UNIT 1, 6.08339 x 10 n/cm 2 , UNIT 2, 6.30491 x 10 18 n/cm 2 (4/16/85).

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection

'--- No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks

1. 2 B Longitudinal and Volumetric 0% 5% of the length of the The required examinations may be circumferential circumferential welds; made at or near the end of the welds in shell 10% of the length of the 10-year inspection interval.

(other than those longitudinal welds of Category A and C) and meridional and circumferen-tial seam welds in bottom head and closure head (other than those of Category C)

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl.20 BA HEAD WELDS VOLUMETRIC 1ST: 16%-34% 100% OF WELD LENGTH DEFERRAL OF THE INSPECTION TO CIRCUMFERENTIAL 2ND: 50%-67% END OF INTERVAL. PERMISSIBLE MERIDIONAL 3RD: 100% FOR BOTTOM HEAD ONLY.

(ACCESSIBLE LENGTH OF ONE WELD EACH.) (FIG.

NO. IWB 2500-3)

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection

  • No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.3 C Vessel-to-flange Volumetric 33% of the length of 100% of the length of Both of these welds are and head-to- the circumferential the circumferential available for examination during flange circum- welds welds normal refueling operations.

ferential welds CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl.30 BA SHELL-TO-FLANGE VOLUMETRIC 1ST: 50%; 3RD: 50% 100% WELD LENGTH PARTIAL DEFERRAL, IF PARTIAL WELD EXAMINATIONS CONDUCTED ON FLANGE Bl.40 HEAD-TO-FLANGE FACE, THE REMAINING VOLUMETRIC WELD (FIG. NO. EXAMINATIONS REQUIRED TO BE IWB-2500-4,5) CONDUCTED FROM VESSEL WALL MAY BE PERFORMED AT OR NEAR END OF INSPECTION INTERVAL.

COMMENTS: 1. SHELL-TO-FLANGE EXAMS CONDUCTED IN CONJUNCTION WITH NOZZLE EXAMINATIONS OF CATEGORY B-D.

2. MINOR DIFFERENCES, ADDITION OF SURFACE EXAMINATION FOR HEAD-TO-FLANGE WELD CONSIDERED MORE RESTRICTIVE. USE OF PARTIAL DEFERRAL CONSIDERED LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods *s-Year Interval During 10-Year Interval Remarks 1.4 D Primary nozzle-to Volumetric 100%*of coverage of a 100% of the remaining The coolant inlet nozzles-to-vessel welds and coolant outlet coolant outlet shell welds and radius sections nozzle-to-vessel nozzle-to-shell weld nozzle-to-shell welds will be examined at the same inside radiused and inner nozzle radii and inner radius time as the welds in Category A.

section sections and 100% of the coolant inlet nozzles-to-shell welds and radius sections CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B3.90 B-D REACTOR VESSEL 1ST: 25-50%, INCLUDES NOZZLE-TO- IF EXAMINATIONS ARE B3.100 NOZZLE-TO-VESSEL THEN 100% BY VESSEL WELD AND ADJA- CONDUCTED FROM INSIDE WELDS END OF 3RD CENT AREAS OF NOZZLE THE COMPONENT AND THE NOZZLE-TO-INSIDE PERIOD AND VESSEL NOZZLE WELD IS EXAMINED RADIUS SECTION BY STRAIGHT BEAM ULTRA-(ALL NOZZLES) SONIC METHOD FROM THE (FIG. NO. NOZZLE BORE, THE REMAIN-IWB-2500-7) 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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.5 E-1 Vessel penetra- Volumetric 0% 25% No meaningful volumetric examina tions, including tions can be performed on the control rod drive control rod drive penetrations penetrations and at this time. Volumetric exam-control rod ination of the instrument housing pressure penetrations in the. bottom head boundary welds will be performed dependent upon development of acceptable equip-ment.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl4.10 B-0 REACTOR VESSEL VOLUMETRIC 1ST: 16-34% 10% OF PERIPHERAL CRD DEFERRAL OF INSPECTION TO END OF WELDS IN CRD OR SURFACE 2ND: 50-67% HOUSINGS INTERVAL PERMISSIBLE.

HOUSING 3RD: 100% (OF 10%)

(FIG. NO. IWB-2500-18)

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Ex_amina t ion Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks

1. 6 E-2 Vessel penetra- Visual 0% 25% The examination will be a visual tions, including examination for evidence of control rod drive leaking at the time of the penetrations and system hydrostatic test at or control rod hous- near the end,of the inspection ing pressure interval.

boundary welds CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B4 .10 B-3 PARTIAL PENETRA- VISUAL, VT-2 1ST: 16-34% 25% EXAMINATION TO BE CONDUCTED WITH TION WELDS CORRESPONDING PRESSURE TEST.

B4.ll VESSEL NOZZLES B4.12 CONTROL ROD DRIVE NOZZLES B4.13 INSTRUMENTATION NOZZLES (EXTERNAL SUR-FACES)

COMMENTS: PRESSURE TEST ESSENTIALLY THE SAME.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks

1. 7 F Primary nozzles Visual and 100% of the dissimilar 100% of the remaining The dissimilar metal welds of to safe and welds surface metal weld on one coolant outlet nozzle each nozzle will be volume-volumetric coolant outlet nozzle dissimilar metal welds trically examined at the same will be volumetrically and 100% of the coolant time as the nozzle-to-shell examined inlet nozzle dissimilar weld, as Bpecified in Category metal welds D.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS BS .10 B-F REACTOR VESSEL VOLUMETRIC, 1ST: 16-34% 100% ALL WELDS THE EXAMINATIONS MAY BE PER-NOMINAL PIPE SIZE SURFACE 2ND: 50-67% FORMED COINCIDENT WITH THE

>4 IN. 3RD: 100% VESSEL NOZZLE EXAMINATION NOZZLE-TO-SAFE REQUIRED BY EXAMINATION CATEGORY END BUTT WELDS B-D.

(ALL)

(FIG. NO. IWB 2500-8)

COMMENTS: 1. STATION PROCEDURE REQUIRES A VISUAL PRIOR TO CONDUCTING A SURFACE EXAM.

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Y.ear Interval During 10-Year Interval Remarks 1.8 G-1 Closure studs and Volumetric and 33% 100% Vessel studs and nuts would be nuts visual or sur- inspected volumetrically and by face surface techniques as required.

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

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B6.10 B-G-1 CLOSURE HEAD NUTS SURFACE 1ST: 16-34% 100% ALL BOLTS, STUDS, DEFERRAL OF INSPECTION TO END OF B6.20 CLOSURE STUDS, IN VOLUMETRIC 2ND: 50-67% NUTS INTERVAL PERMISSIBLE.

B6.30 PLACE SURFACE AND 3RD: 100%

CLOSURE STUDS, VOLUMETRIC WHEN REMOVED (FIG. NO. 2500-12)

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks

1. 9 G-1 Ligaments between Volumetric 33% of the vessel-to- 100% of the vessel The ligaments will be examined threaded stud flange bolt ligaments flange bolt ligaments at the same time as the flange holes will be examined will be examined weld of Item No. 1.3.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO EXAMINATION EXISTS IN 80W80 CODE, THEREFORE LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.10 G-1 Closure washers, Visual 33% 100% None.

bushings CODE EQUIVALENT ITEM. 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS ,EXAM FOR INTERNAL REMARKS B6.50 B-G-1 CLOSURE WASHERS, VISUAL, VT-1 1ST: 16-34% 100% ALL WASHERS, DEFERRAL OF INSPECTION TO END OF BUSHINGS (SUR- 2ND: 50-67% BUSHINGS INTERVAL PERMISSIBLE.

FACES) 3RD: 100%

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

  • ~,

.TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.11 G-2 Pressure retain- Visual Not applicable Not applicable There are no pressure retaining ing bolting bolts less than 2 inches on the Surry Reactor vessels.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL 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 .

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.12 M Internally welded Volumetric (See remarks) (See remarks) These welds are covered by the vessel supports examinations of Category D.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: THESE WELDS STILL COVERED BY THE EXAMINATIONS OF CATEGORY B-D.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.13 I-1 Closure head Visual and 2 patches 6 patches During the 10-year period, at cladding surface or least 6 patches (each 36 square volumetric inches) evenly distributed in the vessel head would be examined.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO CORRESPONDING EXAMINATION REQUIREMENT IN THE 80W80 CODE, CONSIDERED LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.14 I-1 Vessel cladding Visual None 6 patches During the 10-year period, at least 6 patches (each 36 square inches) evenly distributed in the vessel head would be visually inspected.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO CORRESPONDING EXAMINATION IN THE 80W80 CODE, CONSIDERED LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Reguired Reguired Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 1.15 M Interior surfaces Visual A critical examination The inspection made at The examination will include and internals and will be made of the the 4th refueling cycle internal support attachments integrally welded interior surfaces made will be repeated at the welded to the vessel whose.

internal supports available by normal 7th and 10th refueling failure may adversely affect refueling operations cycle core integrity provided these at the 1st refueling are available for visual cycle. This will be examination by components repeated at the 4th removed during normal refueling refueling cycle with operations.

the amount of the inspection being dependent u~on results of the 1st inspection and that made on other pressurized-water systems.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl3.10 B-N-1 REACTOR VESSEL VISUAL, VT-3 1ST: 100% 100% EACH PERIOD NONE.

VESSEL INTERIOR 2ND: 100%

(ACCESSIBLE AREAS 3RD: 100%

ABOVE AND BELOW REACTOR CORE MADE ACCESSIBLE DURING NORMAL REFUELING)

B13.30 B-N-2 REACTOR VESSEL VISUAL, VT-3 1ST: 16-34% ALL WELDS DEFERRAL OF INSPECTION TO END OF CORE SUPPORT 2ND: 50-67% INTERVAL PERMISSIBLE.

STRUCTURE 3RD: 100%

ACCESSIBLE WELDS (STRUCTURE REMOVED)

B-N-3 ACCESSIBLE VISUAL, VT-3 ALL SURFACES SURFACES (STRUCTURE REMOVED)

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

  • TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Exainination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.1 B Longitudinal and Visual and 5% of the length of By the end of the None.

circumferential volumetric the circumferential 10-year period, 10%

welds weld joining the lower of the length of the head to the barrel longitudinal and 5% of section and 10% of the the length of the length of the adjoin- circumferential weld ing longitudinal weld would be inspected.

would be examined.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B2.10 B-B PRESSURIZER VOLUMETRIC 1ST: 16-34% 100% (CIRCUMFERENTIAL) NONE SHELL-TO-HEAD 2ND: 50-67%

WELDS 3RD: 100% !FT (LONGITUDINAL)

B2.11 CIRCUMFERENTIAL (ALL WELDS)

B2.12 LONGITUDINAL (IFT. OF WELD WHICH INTERSECTS CIRCUMFERENTIAL WELD)

(IWB-2500-1,2)

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.2 D Nozzle-to-vessel Visual and Not applicable Not applicable There are no nozzle-to-head welds volumetric welds, as the nozzles are integrally cast with the heads.

Instrument and sample nozzles are included in Category E.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS BJ .110 B-D PRESSURIZER VOLUMETRIC 1ST: 16-34% ALL NOZZLES NOZZLES ARE INTEGRALLY CAST. IF NOZZLE-TO-VESSEL 2ND: 50-67% EXAMINATIONS ARE CONDUCTED FROM WELDS 3RD: 100% INSIDE THE COMPONENT AND THE BJ.120 NOZZLE INSIDE NOZZLE WELD IS EXAMINED BY RADIUS SECTION STRAIGHT BEAM ULTRASONIC METHOD (INCLUDES NOZZLE- FROM THE NOZZLE BORE, THE TO-VESSEL WELD REMAINING SHELL EXAMS MAY BE AND ADJACENT CONDUCTED AT OR NEAR THE END OF

. AREAS OF NOZZLE THE INSPECTION INTERVAL.

AND VESSEL.) FIG.

NO. IWB-2500-?(d)

COMMENTS: EXAMINATION CONSIDERED MORE RESTRICTIVE SINCE NO EXAM PREVIOUSLY REQUIRED.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.3 E-1 Neater connec- Visual and (See remarks) (See remarks) These connections are considered tions surface in Item 2.4.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO SURFACE EXAMINATION CURRENTLY REQUIRED BY 80W80 CODE, THEREFORE REMAINS THE SAME .

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.4 E-2 Neater connec- Visual and (See remarks) (See remarks) These connections are considered tions surface in Item 2.4.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B4.20 B-E PRESSURIZER VISUAL, VT-2 1ST: 16-34% 25% OF THE PENETRATIONS CONDUCTED WITH PRESSURE TEST.

HEATER PENETRA- 2ND: 50%-67%

TION WELDS 3RD: 100%

(EXTERNAL SUR- (of 25%)

FACES)

COMMENTS: EXAMINATION REQUIREMENTS REMAINS THE SAME.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks F Pressure contain- Volumetric 100% of the weld join- 100% of the weld joining Although this item is not re-ing dissimilar ing the surge line to the surge line to the quired in the code, it is felt metal welds the outlet nozzle outlet nozzle and of the that dissimilar metal welds and would be volumetric- weld joining the spray stainless steel safe ends on the ally examined by the line to the nozzle in pressurizer should be examined.

end of the 5-year the upper head would be interval examined CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF REMARKS NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL B5.10 B-F PRESSURIZER VOLUMETRIC, 1ST: 16-34% ALL WELDS NONE.

NOMINAL PIPE SIZE SURFACE 2ND: 50-67% 100%

>4 IN. 3RD: 100%

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

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.5 G-1 Pressure retain- Visual and Not applicable Not applicable There is no bolting 2 inches and ing bolting volumetric larger in diameter on the Surry pressurizer.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS . EXAM FOR INTERNAL REMARKS COMMENTS: BOLTS 1.875 INCHES IN DIAMETER, THEREFORE NOT APPLICABLE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.6 G-2 Pressure retain- Visual 33% by end of 5-year Cumulative 100% by end The bolting below 2 inches in ing bolting interval of interval 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF REMARKS NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL B7.20 B-G-2 PRESSURIZER VISUAL, VT-1 1ST: 16-34% ALL'BOLTING BOLTING MAY BE EXAMINED:

BOLTS, STUDS, NUTS 2ND: 50-67% 100% A) IN PLACE UNDER TENSION:

3RD: 100% B) WHEN THE CONNECTION IS (CATEGORY B-G-2 DISASSEMBLED; TOTAL) C) WHEN THE BOLTING IS REMOVED.

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.7 H Integrally welded Visual and Not applicable Not applicable There are no integrally welded vessel supports volumetric vessel supports on the Surry pressurizer.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF REMARKS NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL COMMENTS: NOTE 1: NO INTEGRALLY WELDED ATTACHMENT.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 2.8 I-2 Vessel cladding Visual None 1 patch (36 square A selected patch of the inches) pressurizer cladding would be visually examined when entry into the vessel is made available for necessary maintenance.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF REMARKS NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL COMMENTS: NO VESSEL CLADDING INSPECTION REQUIRED BY 80W80 CODE, THEREFORE LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.1 B Longitudinal and Visual and 5% of the length of By the end of the None.

circumferential volumetric the circumferential interval, 5% of the welds, including weld joining the lower length of all of the tube sheet-to- primary head to the welds joining the head or shell tube sheet of one primary heads to the welds on the steam generator would tube sheets would be primary side be inspected. inspected.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B2.40 B-B TUBESHEET-TO-HEAD VOLUMETRIC 1ST: 16-34% 100% NONE.

,WELD (FIG. NO. 2ND: 50-67% ALL WELDS IWB-2500-6) 3RD: 100% (3 S/G)

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.2 D Primary nozzle- Visual and (See remarks) (See remarks) There are no nozzle-to-head to-vessel head volumetric welds in the primary heads of welds and the steam generators as the nozzle-to-head nozzles are integrally cast with inside radiused the head.

section CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF REMARKS NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL B3 .130 B-D STEAM GENERATORS VOLUMETRIC 1ST: 25-50% ALL NOZZLES IF EXAMINATIONS ARE CONDUCTED NOZZLE-TO-VESSEL REMAINING BY (INCLUDES NOZZLE-TO- FROM INSIDE THE COMPONENT AND WELDS END OF 3RD VESSEL WELD AND ADJACENT THE NOZZLE WELD IS EXAMINED BY B3.140 B-D NOZZLE-TO-INSIDE PERIOD AREAS OF NOZZLE AND STRAIGHT BEAM ULTRASONIC METHOD RADIUS SECTION VESSEL) FROM THE NOZZLE BORE, THE RE-(FIG. NO. IWB- MAINING SHELL EXAM MAY BE 2500-7d) CONDUCTED AT OR NEAR THE END OF THE INTERVAL.

COMMENTS: EXAMINATION CONSIDERED MORE RESTRICTIVE SINCE NO EXAM PREVIOUSLY REQUIRED.

TABLE 4.2-'-l TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.3 F Primary nozzle- Visual and (See remarks) (See remarks) The primary nozzles are a but-to-safe and welds surface and tered and preparation and the volumetric weld is located between the cast nozzle and a cast elbow.

Volumetric inspection is dependent upon meaningful examination techniques.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B5.30 B-F STEAM GENERATOR VOLUMETRIC, 1ST: 16-34% 100% NONE.

NOMINAL PIPE SURFACE 2ND: 50-67% ALL WELDS SIZE )4 IN. 3RD: 100%

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

COMMENTS: EXAMINATION NOW REQUIRED, MORE RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection

  • No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.4 G-1 Pressure retain- Visual and Not applicable Not applicable There is no pressure-retaining ing bolting volumetric bolting greater than two inches in diameter on the steam generators.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: BOLTING 1.88 INCHES DIAMETER ( PRIMARY MANWAT), THEREFORE NOT APPLICABLE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.5 G-2 Pressure retain- Visual 33% by end of 5-year Cumulative 100% by end The bolting below 2 inches in ing bolting interval of interval 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl .30 B-G-2 STEAM GENERATORS VISUAL, VT-1 1ST: 16-34% ALL BOLTS, STUDS, NUTS BOLTING MAY BE EXAMINED BOLT, STUDS, NUTS 2ND: 50-67% (3 S/G) (A) IN PLACE UNDER TENSION:

(SURFACE) 3RD: 100% (B) WHEN THE CONNECTION IS (CATEGORY B-G-2 DISASSEMBLED:

TOTAL) (C) WHEN THE BOLTING IS REMOVED.

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.6 H Integrally welded Visual and Not applicable Not applicable There are no supports integrally vessel supports volumetric welded to the steam generator pressure boundary.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: THERE ARE NO INTEGRALLY WELDED SUPPORTS.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 3.7 I-2 Vessel cladding Visual None 1 patch (36 square A visual examination would be inches) made only such time as the primary side is opened for necessary maintenance.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: THERE IS NO CORRESPONDING CODE INSPECTION, THEREFORE CONSIDERED LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.1 F Vessel-, pump-, Visual and (See remarks) By the end of the Examination of these welds is and valve-safe surface and interval, a cumulative covered under Section A, B, and ends-to-primary volumetric 100% of the welds would C and explained in the discus-pipe welds and have been examined sion.

safe ends in branch piping welds CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: SAFE END EXAMINATIONS ONLY ASSOCIATED WITH REACTOR VESSEL, PRESSURIZER OR STEAM GENERATOR.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interva:). During 10-Year Interval Remarks 4.2 J-1 Circumferential Visual and 5% of the circumferen- By the end of the None.

and longitudinal volumetric tial welds, including interval, a cumulative pipe 'welds and one foot of any longi- 25% of the circumferen-branch pipe tudinal weld on either tial welds in the piping connection welds side of the butt weld, system would have been larger than 4 would be examined examined, including one inches in foot of any longitudinal diameter weld on either side of the butt welds CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B9.10 B-J NOMINAL PIPE SURFACE AND 1ST: 16-34% 80W80 UTILIZES SELECTION 10CFR 50.55a REQUIREMENTS ALLOWS SIZE ~4 IN. VOLUMETRIC 2ND: 50-67% PROCESS BASED ON STRESS, USE OF 74S75 CODE FOR EXTENT OF B9.ll CIRCUMFERENTIAL 3RD: 100% MATERIAL AND LOCATION. EXAMINATION AND EXEMPTIONS.

WELDS (OF EXTENT) 100% OF SELECTED B9.12 LONGITUDINAL CIRCUMFERENTIAL WELDS WELDS AND AT LEAST A PIPE (FIG. NO. DIAMETER LENGTH BUT NOT IWB-2500-8) MORE THAN 12 INCHES OF B9.31 BRANCH PIPE SELECTED LONGITUDINAL CONNECTION WELDS WELDS AT THE CIRCUM-

~4 IN. FERENTIAL WELD INTER-SECTION COMMENTS: 1. SURRY CURRENTLY USES 74S75 OPTION.

2. ADDITIONAL SURFACE REQUIREMENT, THEREFORE.MORE RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.3 G-1 Pressure retain- Visual and Not applicable Not applicable There is no bolting 2 inches and ing bolting volumetric larger in the piping system.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: THERE IS NO BOLTING GREATER THAN 2 INCHES ON PIPING.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.4 G-2 Pressure retain- Visual 33% of the bolting By the end of the All bolting is below 2 inches in ing bolting would be examined interval, 100% of the diameter and would be visually bolting would be examined, either in place if the examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B7.50 B-G-2 PIPING VISUAL, VT-1 1ST: 16-34% 100% BOLTING MAY BE EXAMINED:

BOLTS, STUDS, 2ND: 50-67% ALL BOLTS, STUDS, AND (A) IN PLACE UNDER TENSION NUTS (SURFACE) 3RD: 100% NUTS (B) WHEN THE CONNECTION IS (OF B-G-2 DISASSEMBLED CATEGORY) (C) WHEN BOLTING IS REMOVED.

COMMENTS: REMAINS ESSENTIALLY THE SAME.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.5 K-1 Integrally welded Visual and 10% of supports would By the end of the Areas subject to examination supports surface be examined interval, a cumulative would include any integrally 25% of the supports welded external support would be examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl0.10 B-K-1 PIPING VOLUMETRIC 1ST: 16-34% EXAMINATION INCLUDES ALL INCLUDES THOSE ATTACHMENTS WHOSE INTEGRALLY WELDED OR SURFACE 2ND: 50-67% WELDED ATTACHMENTS OF ATTACHMENT BASE MATERIAL DESIGN ATTACHMENTS AS APPLICABLE 3RD: 100% PIPING SELECTED FOR EXAM THICKNESS IS 5/8 INCH AND (FIG. NO. 2500-13, (OF SELECTION) IN CATEGORY B-J GREATER ONLY. INSPECTION ENDS 14 and 15) 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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.6 K-2 Piping support Visual 33% of the supports By the end of the The support members and struc-and hanger would be examined interval, a cumulative tures subject to examination 100% of the supports would include those supports would be examined within the system whose structural integrity is relied upon to withstand the design loads and seismic-induced displacements.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS SUPPORT PROGRAM UNDER DEVELOPMENT WILL VISUAL, VT-3, PERIOD AND INTERVAL REQUIREMENTS WILL CORRESPOND AS REQUIRED BY IWF OF ASME USE THE REQUIREMENTS OF CATEGORY FA, FB, VT-4 AS TO THE REQUIREMENTS OF IWB, IWC AND IWD FOR THE SECTION XI USE OF MULTIPLE AND FC OF THE 80W81 CODE APPLICABLE COMPONENT/PIPING THAT THE SUPPORT IS ATTACHED TO COMPONENT DESIGNATION ALLOWED, LIMITING EXAM TO ONE TRAIN.

COMMENTS: 1. PRIOR TO PROGRAM IMPLEMENTATION RULES OF 74S75 B-K-2 REQUIRED.

2. FREQUENCY CURRENTLY USES A THIRD PER PERIOD OF ALL SUPPORTS.
3. EVENTUAL IWF 80W81 WILL PROVIDE A MORE COMPREHENSIVE EXAMINATION, MORE RESTRICTIVE, BUT LESS SUPPORTS SELECTED, LESS RESTRICTIVE
  • TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.7 J-2 Circumferential Visual 50% of the welds would By the end of the and longitudinal be examined inspection interval a pipe welds and cumulative 100% of the branch pipe welds and pipe branch connections connections would be examined.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO CORRESPONDING EXAMINATION IN CURRENT CODE 80W80 UNLESS REFERENCING B-P PRESSURE TEST.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspect.ion No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 4.8 J-1 Socket welds and Visual and 5% of the circumferen- By the end of the pipe branch surface tial welds and 5% of inspection interval, a connections welds the pipe branch con- cumulative 25% of the 4 inches in *nection welded joints circumferential welds in diameter and would be examined the piping system and smaller 25% of the pipe branch connections welded joints would be examined CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B9.32 B-J NOMINAL PIPE SIZE SURFACE SELECTION REQUIREMENTS SIMILAR TO LARGER B-J PIPING.

<4 IN.

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

B9.40 SOCKET WELDS SURFACE (FIG. NO. IWB-2500-8)

COMMENTS: SELECTION CURRENTLY USES 74S75 REQUIREMENTS WHICH IS ESSENTIALLY THE SAME. USE OF 80W80 EXTENT OF EXAMINATION LESS RESTRICTIVE .

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.1 L-1 Pump casing welds Visual and None None The only feasible method known volumetric 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl2 .10 B-L-1 PUMP CASING WELDS VOLUMETRIC N/A 1 PUMP, DEFERRAL TO END NONE.

OF INTERVAL PERMISSIBLE COMMENTS: 1. RADIOGRAPHY CONDUCTED THE FIRST INTERVAL.

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.2 L-2 Pump casings Visual None By the end of the The only pumps involved in this interval, a cumulative program are the coolant pumps.

100% of the available inner surfaces of the required pumps would be examined if the pumps are disassembled for maintenance CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl2.20 B-L-2 PUMP CASING VISUAL, VT-3 N/A EXAMINATION WOULD BE NONE.

(INTERNAL CONDUCTED IN CONJUNC-SURFACES) TION WITH REQUIRED VOLUMETRIC EXAM.

COMMENTS: 1. RELIEF MAY BE REQUESTED TO LIMIT THIS EXAMINATION TO COINCIDE WITH MAINTENANCE DISASSEMBLY.

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. *Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.3 F Nozzle-to-safe Visual and Not Applicable Not Applicable There are no nozzle-to-safe end end welds volumetric welds on the pumps.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: THERE ARE NO NOZZLE-TO-SAFE END WELDS ON THE PUMPS .

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.4 G-1 Pressure retain- Visual and (See remarks) By the end of the Bolting 2 inches and larger in ing bolting volumetric interval, a cumulative diameter would be examined 100% of the bolting either in place under tension, would be examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B6.180 B-G-1 BOLTS AND STUDS VOLUMETRIC 1ST: 16-34% ALL BOLTS, STUDS, NUTS, DEFERRAL OF INSPECTION TO END OF (FIG. NO, IWB- 2ND: 50-67% BUSHINGS, THREADS IN INTERVAL PERMISSIBLE.

2500-12) 3RD: 100% FLANGE STUD HOLES BOLTING MAY BE EXAMINED:

B6.190 FLANGE SURFACE, (A) IN PLACE UNDER TENSION:

WHEN CONNECTION (B) WHEN THE CONNECTION IS DISASSEMBLED DISASSEMBLED:

(SURFACES, (C) WHEN BOLTING IS REMOVED.

INCLUDING 1 IN.

ANNULAR SURFACE OF FLANGE SURROUNDS EACH STUD)

B6.200 NUTS, BUSHINGS, WASHERS (SURFACES)

COMMENTS: 1, I.E. BULLETIN 82-02 REQUIRES SURFACE EXAM ON BOLTS OR STUDS WHEN REMOVED.

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection

, No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.5 G-2 Pressure retain- Visual (See remarks) By the end of the Bolting below 2 inches in ing bolting interval, a cumulative diameter would be visually 100% of the bolting ' examined, whenever the bolted would be examined connection is disassembled for maintenance purposes. *The bolting to be examined would include studs and nuts.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B7 .60 B-G-2 BOLTS, STUDS, VISUAL, VT-1 1ST: 16-34% ALL BOLTS, STUDS, AND BOLTING MAY BE EXAMINED:

NUTS (SURFACE) 2ND: 50-67% NUTS (A) IN PLACE UNDER TENSION, 3RD: 100% (B) WHEN THE CONNECTION IS (CATEGORY B-G-2 . DISASSEMBLED TOTAL) (C) WHEN BOLTING IS REMOVED.

GCJMMENTS: 1. IE BULLETIN 82-02 REQUIRES SURFACE EXAM ON BOLTS OR STUDS.

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

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.6 K-1 Integrally welded Visual and 10% of the supports By the end of the None.

supports volumetric would be visually interval, a cumulative examined 25% of the supports would be visually examined CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl0.10 B-K-1 PUMPS VOLUMETRIC OR 1ST: 16-34% 100% WELDED ATTACHMENTS INSPECTION ENDS AFTER SECOND INTEGRALLY WELDED SURFACE AS 2ND: 50-67% WHERE BASE MATERIAL INTERVAL.

ATTACHMENTS APPLICABLE 3RD: 100% DESIGN THICKNESS IS 5/8 (FIG. NO. 2500-13, IN. AND GREATER 14, 15)

COMMENTS: 1. SURFACE REQUIREMENT COULD BE LESS RESTRICTIVE, NO INSPECTION AFTER 2ND INTERVAL, LESS RESTRICTIVE.

2. BASE MATERIAL REQUIREMENT, LESS RESTRICTIVE.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.7 K-2 Supports and Visual 33% of the supports Cumulative 100% of the None.

hangers would be examined supports would be examined CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: COMMENTS OF SUPPORT PROGRAM ITEM 4.6 REMAIN THE SAME FOR THIS ITEM.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.1 H-1 Valve body welds Visual and Not applicable Not applicable All the valves subject to this volumetric inspection are cast valves, thus this item is not applicable.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: ALL VALVES STILL SUBJECT TO THIS INSPECTION ARE CAST VALVES.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 5.8 Primary pump Visual and (See remarks) 100% examination at or All flywheels shall be visually Flywheel Volumetric near the end.of the examined at the first refueling inspection interval *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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: 1. NO CORRESPONDING CODE 80W80 EXAM, LESS RESTRICITVE.

2. TECHNICAL SPECIFICATION CHANGE ENDORSES INSPECTION PER REGULATORY POSITION C.4.B. OF REG. GUIDE 1.14 REV. 1, AUGUST 1975, MORE RESTRICTIVE
  • TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.2 H-2 Valve bodies Visual (See remarks) By the end of the The valves subject to this in-interval, a cumulative spection may be examined during 100% of the available maintenance or at the end of inner surfaces of the each interval.

required valves would be examined CODE EQUIVALENT ITEM 2ND* INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS Bl2.40 B-M-2 VALVE BODY EXCEED- VISUAL, VT-3 1ST: 16-34% 100% DEFERRAL OF INSPECTION TO END OF ING 4 IN. *2ND: 50-67% INTERNAL SURFACE, INTERVAL, PERMISSIBLE.

NOMINAL PIPE SIZE 3RD: 100% LIMITED TO ONE VALVE (INTERNAL SUR- WITHIN EACH GROUP OF FACES) VALVES THAT ARE OF THE SAME CONSTRUCTIONAL DESIGN, MANUFACTURING METHOD AND FUNCTION (SIMILAR)

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.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.3 F Valve-to-safe and Visual and Not applicable Not applicable There are no valves in this welds volumetric system with dissimilar metal welds.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO DISSIMILAR METAL WELDS IN .THIS CATEGORY.

TABLE 4,2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.4 G-1 Pressure retain- Visual and (See remarks) By the end of the Bolting 2 inches and larger in ing bolting volumetric interval, a cumulative diameter would be examined 100% of the bolting 2 either in place under tension or inches and larger would when the bolting is removed or be examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO VALVES ARE IN CATEGORY B-M-1, THEREFORE NO BOLTING IS REQUIRED TO BE EXAMINEP IN B-G-1, LESS RESTRICTIVE,

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.5 G-2 Pressure retain- Visual and 33% By the end of the All bolting is below 2 inches in ing bolting volumetric interval, cumulative diameter and would be visually 100% of the bolting examined, either in place if the would be examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS B7.70 B-G-2 VALVE VISUAL, VT-1 1ST: 16-34% ALL BOLTS, STUDS, AND BOLTING MAY BE EXAMINED:

BOLTS, STUDS, 2ND: 50-67% NUTS (A) IN PLACE UNDER TENSION, NUTS (SURFACE) 3RD: 100% (B) WHEN THE CONNECTION IS (OF B-G-2) DISASSEMBLED, (C) WHEN THE BOLTING IS REMOVED.

COMMENTS: EXAMINATION REMAINS ESSENTIALLY THE SAME

  • TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.6 K-1 Integrally welded Visual and Not applicable Not applicable There are no integrally-welded supports volumetric supports on the valves subject to this examination.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NO INTEGRALLY WELDED SUPPORTS ON THE VALVES.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 6.7 K-2 Supports and Visual 33% of the supports By the end of the The support members and struc-hangers and hangers would be interval, a cumulative tures subject to examination examined 100% of the supports and would include those supports for hangers would be piping, valves, and pumps within examined 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.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: COMMENTS ON THE SUPPORT PROGRAM IN ITEM.4.6 REMAIN THE SAME FOR THIS ITEM

  • TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 7.1 Materials Tensile and Capsule 1 shall be Capsules shall be Capsule 4 shall be removed and Irradiation Charpy V removed and examined removed and examined examined after 20 years.

Surveillance notch (wedge at the first region after 10 years Capsules 5-8 are extra capsules open loading) replacement. Capsule for complementary or duplicate and Dosimetry 2 shall be examined testing.

after 5 years.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: NOT CHANGED, REMAINS ON TABLE 4.2-1.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 7.2 Low Head SIS Visual (See Remarks) Not applicable This pipe shall be visually Piping located in inspected at each refueling valve pit shutdown.

CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: WILL BE COVERED BY CLASS 2, SYSTEM PRESSURE TESTS AND CORRESPONDING VT-2 EXAMINATION, ESSENTIALLY REMAINS THE SAME.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First' Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 7.3 Low pressure Visual and 100% of blades Not applicable turbine rotor magnet part-icle or dye penetrant CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL REMARKS COMMENTS: WILL PUT BACK IN.

TABLE 4.2-1 TECH SPEC ITEM Required Required Extent of Examination Item Examination Examination Planned During First Tentative Inspection No. Category Areas Methods 5-Year Interval During 10-Year Interval Remarks 8.1.1 J-1 Circumferential Visual and Three times the extent Three time the extent of

  • Extent in this context is and longitudinal volumetric of Section D. Item Section D, Item No. 4.2 interpreted to mean that pipe welds and No. 4.2 of Table 4.2-1 of Table 4.2-1 inspections will be conducted at branch pipe three times the inspection connections frequency required by Items 4.2, larger than 4 4.7 and 4.8 of Table 4.2-1.

inches in Thus, those examinations planned diameter for the first five year interval 8.1.2 J-2 Circumferential Three times the Three times the extent for Items 4.2, 4.7 and 4.8 will and longitudinal extent* of Section D, of Section D, Item No. be performed every 1-2/3 years pipe welds and Item No. 4.7 of Table 4.7 of Table 4.2-1 (generally each normal refueling branch pipe 4.2-1 outage). See Transcript of connections Hearing (pp. 303-304) and 8.1.3 J-1 Socket welds and Three times the Three times the extent Initial Decision (p. 7, §10).

pipe branch extent* of Section D, of Section D, Item No. Same as above.

connections welds Item No. 4.8. of Table 4.7 of Table 4.2-1 4 inches in 4.2-1 diameter and smaller CODE EQUIVALENT ITEM 2ND INTERVAL EXAMINATION NORMAL PERIOD EXTENT OF NO. CATEGORY PARTS EXAMINED METHOD REQUIREMENTS EXAM FOR INTERNAL 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

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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.

I.

(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.)

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.)

(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.)

B. Acceptance criteria references ASME Section XI for tests in Specification 4.8.A. (More restrictive than present Technical

    • Specifications.)
  • ,* ( .... ~

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).

  • I