ML13302A471

Forwards Responses to NRC Questions & Revised FSAR Sections Re Preservice & Inservice Insp & Testing

ML13302A471
Person / Time
Site:	San Onofre
Issue date:	10/06/1980
From:	Baskin K Southern California Edison Co
To:	Miraglia F Office of Nuclear Reactor Regulation
Shared Package
ML13302A473	List: ML13302A471 ML13302A474 ML19351C968
References
NUDOCS 8010080454
Download: ML13302A471 (68)

Text

REGULAT IORAIN DISTRIBUTIOtYSTEM( (RIDS)

INFORMATIO ACCESSION NBR:8010080454 DOC.DATE9 80/10/06 NOTARIZED: NO DOCKET #

FACIL:50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361

'50-362 San Onofre Nuclear'Station, Unit 3, Southern Californ 05000362 AUTH.NAME AUTHOR AFFILIATION BASKINK,P. Southern California Edison Co.

RECIPNAME RECIPIENT AFFILIATION MIRAGLIAF. Licensing Branch 3

SUBJECT:

Forwards responses to NRC questionstrevised FSAR sectionstre preservice insp & inservice testing programs are available in Central Files only.

DISTRIBUTION CODE: 80018 COPIES RECEIVED:LTR X ENCL SIZE:L TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES:Send all FSAR & ER amends to L Chandler. 05000361 41H-m it~R Sf64 amemo te L ChaM 1 ~ , 05000362 RIVItN gA Cy 7b Fit6S RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LT ENIC ME4 LTTR ENCL ACTION: A/D LICENSNG 1 0 SCHWENCERPA. 1 0 LEEJ. 1 0 ROODH, 04 1 1 INTERNAL: ACCID EVAL 8R26 1 1 AUX SYS BR 07 1 1 CHEM ENG BR 08 1 1 CONT SYS BR 09 1 1 CORE PERF BR .10 1 1 EFF TR SYS BR12 I 1 EMERG PREP 22, 1 0 EQUIP QUAL 8R13 1 1 GEOSCIENCES 14 1 1 HUM FACT ENG BR 1.

HYD/GEO BR 15 2 2 I&C SYS BR 16 1 1 I&E 06 3 3 LIC GUID BR 1 1 LIC QUAL BR 1 1 MATL ENG BR 17 1 1 MECH ENG BR 18 1. 1 MPA 1 0 NRC PDR 02 1 1 OELD 1 0 OP LIC BR 1 1 POWER SYS BR 19 1 1 PROC/TST REV 20 1 1 QA BR 21 1 1 RA 'SS BR22 1 1 REAC SYS BR- 23 1 1 01 1 .1 SIT ANAL BR 24 1 1 RUCT ENG BR25 1 1 SYS INTERAC BR I 1 EXTERNAL: ACRS 27 16 16 LPDR 03 1 1 NSIC 05 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 55 ENCL 49

Southern California Edison Company P. 0. BOX 800 2244 WALNUTGROVEAVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE S *-ER OF NUCLEAR ENGINEERING, October 6, 1980 (213) 572-1401 SAFETY. AND LICEN5'f.3 Director of Nuclear Reactor Regulation Attention: Mr. Frank Miraglia, Branch Chief

- Licensing Projects Branch 3 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3.

Enclosed are sixty-three (63) copies of responses to several NRC questions and revised FSAR sections related to preservice and inservice inspection and testing. Direct distribution of these responses will be made as part of Amendment 21 distribution and will be in accordance with the service list provided by SCE's letter of October 29, 1979. An affidavit attesting to the fact that distribution has been completed will be provided within ten (10) days of docketing of Amendment 21.

Also enclosed are: 1) Seven (7) copies of the Preservice Inspection Program Plan, and 2) seven (7) copies of the Inservice Testing Program referenced in-the-response to.-question 121.17. _Section 1.8 of the FSAR will be updated to reflect the submittal of these documents; however, additional copies will not be provided.

Please let me know if you have any questions.

Very truly yours, Enclosure O bcA

PRESERVICE INSPECTION AND INSERVICE TESTING San -Onofre. Nuclear_ Generating. Station Units 2 and 3 October 6, 1980 CE Standard Technical Specification 3.4.4.11 (July 1980)

Surveillance Requirements for Inservice Inspection and Testing.

Responses to NRC Questions Q 121.3, Revision Q 121.8, Revision Q 121.9, Revision Q 121.16 Q 121.17..

Table,-3 -28 FSAR Sections 3.9.6 Inservice Testing of Pumps and Valves 5.2.4 Inservice Inspection of Reactor Coolant Pressure Boundary Components 5.4.2.4.2. - .Steam.Generator- Inservice:-Inspection--.

6.6 Inservice Inspection of Class 2 and 3 Components

REACTOR COOLANT SYSTEM 3.4.11 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.11 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.11.

APPLICABILITY: ALL MODES ACTION:

a. With the structural integrity of any ASME Code Class I component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50oF above the minimum temperature required by NDT considerations.

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) prior to increasing the Reactor Coolant System temperature above 200 0 F.

c. With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.11 In addition to the requirements of Specification 4.C.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations .of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

CE-STS 3/4 4-32

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specificaton shall exist when the requirements of the Limiting Condition for Operation and/or associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, the unit shall be placed in a MODE in which the specification does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

2. At leats HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may. be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the inoividual specifications.

3.0.4 Entry into the OPERATIONAL MODE or other specified condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision whall not prevent passage through OPERATIONAL MODES as required to comply with ACTION statements. Exceptions to these requirements are stated in the individual specifications.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its.redundant system(s), subsystem(s),

train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfie, the unit shall be placed in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This specification is not applicable in MODES 5 or 6.

CE-STS 3/4 0-1

APPLICAEILIIY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, and

b. The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

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

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

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

CE-STS 3/4 0-2

APPLICABILiTY SURVEILLANCE REQUIREMENTS (Continued)

ASME Boiler and Pressure Vessel Code and applicable Required frequencies Addenda terminology for for performing inservice inservice inspection and inspection and testing testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 .days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d. Performance of the above inservice inspection and testing activities shall be in addition ot 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.

CE-STS 3/4 0-3

Responses to NRC Questions San Onofre 2&3 Question 121.3 Considering your CP date of October 1973, your preservice inspection program will be conducted to the more current 1974 edition of Section XI, Summer 1975 Addendum and inservice inspection program will comply with the requirements in the editions of the ASME B&PV Code and Addenda in effect no more than six months prior to the starting date of commercial operation.

However, you state that the ASME Code Class 1, Class 2 or Class 3 shall meet the requirements of the Section XI of editions of ASME B&PV Code and Addenda to the extent practical within the limitations of design, geometry, and materials of construction of the components.

The inservice inspection plan based on current requirements will be reviewed to support the safety evaluation report finding on ISI. Your response should define all the examination requirements that you determine are not practical within the limitations of the design, geometry, and materials of construction of the components. Particular attention should be directed to impractical examinations resulting from revised Section XI requirements in Section 50.55a, paragraph (b), such as examinations that will result in high radiation exposure to personnel without a commensurate increase in safety (1) known inaccessible regions due to component arrange ment, (2) restricted access to welds in accepted ASME Code weld geometry designs, and (3) limitations in examination methods or procedures due to metallurgical properties in approved materials of construction.

Discuss the inservice inspections (or testing) that will be performed in lieu of the ASME Code Section XI requirements that you determine to be impractical. The technical justification to support your conclusions should contain as a minimum (1) the identification of the applicable ASME Code edition(s) and subsection(s), (2) the number of components, (3) the safety significance of postulated failure at the inspection location, (4) the Section XI examination category, (5) the examination method, (6) the degree of conformance, and (7) the system modifications, equipment or conditions that would be necessary for total compliance.

The updated inservice inspection plan should be submitted for review within six months of anticipated commercial operation to demonstrate compliance with 10>CFR Part 50, Section 50.55a, paragraph (g). This plan will be evaluathd in a safety evaluation report supplement. The objective is to supplement the previously submitted inservice inspection plan to incor porate (1)Section XI requirements in effect six months prior to commercial operation and (2) any augmented examination established by the Commission.

Your response should define all examination requirements that you determine are not practical within the limitations of design, geometry, and materials of construction of the components.

Q&R 5.2-1

Question 121.3 Responses to NRC Questions San Onofre 2&3

Response

The preservice inspection program together with any request for relief was submitted to the NRC for review in September 1980. Technical justification was provided for those areas which were determined to be impractical to examine.

As a minimum this information contained (1) the identification of applicable ASME Code edition and addenda, (2) the number of components, (3) the examination category, (4) the examination method, (5) the degree of performance and (6) the alternate method to be used.

Reference Preservice Inspection Program Plan, Appendix A Q&R 5.2-2

' Responses to NRC Questions San Onofre 2&3 Question 121.8 Your response to Question 121.3 to submit the inservice inspection program together with any exceptions.to preservice examination requirements six months prior to commercial operation is not acceptable. We can not com plete the evaluation of your inservice inspection program in the Safety Evaluation Report (SER) without a comparison of your inservice inspection plan with requirements currently referenced in 10 CFR Part 50, Section 50.55a(b).' An inservice inspection program submitted six months from the commercial operation does not provide sufficient time for the technical evaluation and resolution of potential exceptions to the code requirements as implied in your response.

(a) Preservice Inspection Plan - Considering your CP issue date of October 18, 1973, a preservice inspection plan is acceptable based on all re quirements of Section XI, 1 9 7 lEdition including all Addenda through Summer 1972. For ASME Code Class 1 components,Section XI paragraph IS-232 requires a preoperational examination essentially 100% of the pressure-containing welds. Consequently in accordance with 10 CFR 50.55a(a)(2), we will require a complete technical justification for all relief requests from preservice examination requirements for ASME Code Class 1 components to demonstrate either (1) the "hardships or unusual difficulties without a compensating increase in the level of quality and safety" or (2) "proposed alternatives to the described requirements or portions thereof will provide an acceptable level of quality and safety".

You state in Section 5.2.4.1 that the preservice examination for ASME Code Class 1 components will be conducted in accordance with Section XI, 1974 Edison, including all Addenda through Summer 1975. You state in Section 6.6 that the preservice examination for ASME Code Class 2 and 3 components will be conducted, to the extent practical, in accord ance with Section.XI, 1974 Edition, including all Addcnda through Summer 1975. This is acceptable, providing that in instances where upgrading to the 1974 Edition is .notpractical, -thd examinations which are conducted meet at least the preservice requirements contained in the 1971 Edition with Addenda through Summer 1972.

(b) Inservice Inspection Plan - Unless you anticipate no requests for re lief from initial inservice inspection program requirements, your pro posal to submit the inservice inspection program six months prior to commercial operation is not acceptable. We will require a comparison of your inservice inspection plan with the latest Edition of Section XI referenced in the FEDERAL REGISTER, i.e., Summer 1975 Addenda, to complete SER review on ISI. Identify the time schedule when your de sign, component pro'curement and/or construction will have .progressed to submit the specific degree of compliance with the Edition of Section XI in effect as stated in Question 121.3.

Q&R 5.2-7

Question 121.8 Responses to NRC Questions San Onofre 2&3 that an upIated (c) Updated Inservice Inspection Plan - We will.require six months of inservice inspection plan be submitted for review within anticipated commercial operation to demonstrate compliance with 10 CFR Part 50, Section 50.55a, paragraph (g). The objective is to supplement to incorporate the previously submitted inservice inspection plan commercial (1)Section XI requirements in effect six months prior to the operation and (2) any augmented examination established byrequirements response should define all examination that Commission. Your you determine are not practical within the limitations of design, of the components.

geometry, and materials of construction

Response

request for relief was The preservice inspection program together.with any Technical justification was submitted to the NRC for review in September 1980.

impractical to examine.

provided for those areas which were detemined to be The inservice inspection program is being developed to the 1977 Edition through those Summer 1978 Addenda of ASME Section XI - This ISI program includes in identified limitations and modifications required of 10 CFR 50.55a(g) and the October 9, 1979 Federal Register, Volume 44, No. 196.

Since the examinations performed during inservice are the same examinations anticipated.

performed for the preservice, no new exceptions are months As stated in 5.2.4.2, the ISI program will be submitted for review six 120 month inspection before the start of San Onofre's Units 2 and 3 initial interval so that compliance with 10 CFR 50.55a(g) can be demonstrated.

Reference Preservice Inspection Program Plan and revised FSAR paragraph 5.2.4.

Q&R 5.2-8

Responses to NRC Questions San Onofre 2&3 Question 121.9 In FSAR Section 5.2.4.2 you describe an inspection program based on examination categories corresponding to Section XI, 1974 Edition, Summer 1976 Addenda.

This Addenda has not been referenced in 10 CFR Part 50, Section 50.55a(b) and is not acceptable for use without a complete technical justifications from the applicant. We will require that the FSAR be revised to reflect the requirements of the Edition of Section XI referenced in 10 CFR Part 50.

FSAR Section 5.2.4.2.4.C requires particulary clarificaton to define the Examination Method that you propose for Category B-3, Pressure-Retaining Welds in Piping.

Response

FSAR paragraph 5.2.4.3 has been revised to reflect the requirements of ASME Section XI, 1977 Edition through Summer 1978 Addenda. This ISI program includes the limitations and modifications required by the 1980 Edition of 10 CFR 50.55a(b)(2).

FSAR Paragraph 5.2.4.7.9 has been revised to define the examination method for Category B-J, "Pressure Retaining Welds in Piping".

Reference See revised FSAR paragraph 5.2.4.3 and 5.2.4.7.9.

Q&R 5.2-9

Responses to NRC Questions San Onofre 2&3 Question 121.16 as part of the preservice The following information is required to be submittedUnit Nos. 2 and 3.

and inservice inspection programs for San Onofre by Section XI of the A. Confirm that all preservice examinations required for those areas for ASME Code for Class 1 and 2 components were completed which a request for relief is not requested.

for Class' 1 and 2 B. For those preservice and inservice inspections the following information is components for which relief is requested required:

welds that were not

1. Provide the specific location (drawings) of all examination.

subjected to complete Section XI preservice fabrication examination

2. Define the method and extent of the original Section XI for the welds that were not subjected to complete preservice examination.

performed?

3. To what extent were individual Section XI examinations could be

4. What alternate preservice and inservice examinations performed?

to make the welds

5. Describe the measures which would be required Identify accessible for both preservice and inservice examinations. from inservice the ASME Class 1 welds that would not require relief were performed.

examination if surface preparation of the weld crown

Response

The preservice Inspection Program confirms that allwere examinations required by components completed.

ASME Section XI for Code Class I and 2 Appendix A of the preservice Inspection Program describes those components for requirements.

which relief is requested from ASME Section XI examination Reference See revised FSAR sections 5.2.4, 5.4.2.4 and 6.6.

Q&R 5.2-41

Responses to NRC Questions San Onofre 2&3 Question 121.17 We require that your inspection program for Class 1, 2 and 3 components be in accordance with the revised rules in 10 CFR Part 50, Section 50.55a, paragraph (g). Accordingly, submit the following information:

(1) A preservice inspection plan which is consistent with the required edition of the ASME Code. This inspection plan should include any exceptions you propose to the Code requirements.

(2) An inservice inspection plan submitted within six months of the anticipated date for commercial operation.

This preservice inspection plan will .be required to support the safety.

evaluation report finding regarding your compliance with preservice and inservice inspection requirements. Our determination of your compliance will be based on:

(1) That edition of Section XI of the ASME Code referenced in your FSAR or later editions of Section XI referenced in the FEDERAL REGISTER that you may elect to apply.

(2) All augmented examinations established by the Commission when added assurance of structural reliability was deemed necessary. Examples of augmented examination requirements can be found in the NRC positions on:

-(1) high energy fluid systems in Section 3.6 of the Standard Review Plan (SRP), NUREG-75/087; (2) turbine disk integrity in Section 10.2.3 of the SRP; (3) the BWR feedwater inlet nozzle inner radii, NUREG-312, and (4) BWR SS piping NUREG-313.

Your response to this item should define the applicable edition(s) and subsections of Section XI of the ASME Code. If any of the examination requirements of the particular edition of Section XI you referenced in the FSAR cannot be met, a request for relief must be submitted, including complete technical justification to support your request.

Detailed guidelines for the preparation and content of the inspection programs to be submitted for staff review and for relief requests are attached as Appendix A to Section 121.0 of our review questions.

Question 121.17

Response

The presevice inspection program together with any request for relief was submitted to the NRC for review in September 1980. Technical justification was provided for those areas which were determined to be impractical to examine.

This plan is consistent with the required edition of the ASME Code.

The inservice inspection plan is being developed to the 1977 Edition through Summer 1978 Addenda of ASME Section XI. As stated in 5.2.4.2, the ISI program will be submitted for review six months before the start of the initial 120 month inspection interval so that compliance with 10 CFR 50.55a(g) can be demonstrated.

Reference Preservice Inspection Plan and revised FSAR paragraph 5.2.4.

Sai Ounofi o 2&3 FSAR MECHAN I CAL SYSTEMS AND COMPONENTS Table 3.9-28

SUMMARY

OF iiJtPS SERVIED BY STANDBY DIESEL POWER SOURCE REQUIRIN INSERVICE TESTING (Sheet 2 of 2)

ASME, Component Sect ion I1I.

IdentIfIcation(a) Descri.ption Code Class P024 Component cool ing water pump (E) .3 1025 Componlent cool.l.g water pump 3 P026 Vomponent conthig water pump (W) 3 P093 Diesel fuel. transfer pump 3 1P094 Diesel ftuel transfer pump 3 P095 DIesel fuel transfer pump 3 P096 Diesel fuel transfer pump 3 P112 Salt water cooling pump 3 P113 Salt water cooling pump 3 P114 Salt water cooling pump 3 P140 Auxiliary feedwater pump steam 3 P141 Auxiliary feedwater pump motor 3 P160 Auxiliary building emergency 3 chiller water pump P162 Auxiliary building emergency 3 chiller water pump P307 Salt water cooling pump 3 P504 Auxiliary feedwater pump motor 3 3.9-126

0 .ENCLOSURE 1 3.9.6 INSERVICE TESTING OF PUMPS AND VALVES The Inservice Testing Programs for San Onofre Nuclear Gener ating Station, Units 2 and 3, were developed in compliance with the rules and regulations of 10CFR50.55a(g) and submitted to the NRC for review in September 1980.

Section 3.9.6.1 discusses the. program for inservice testing of ASME Class 1, 2 and 3 pumps which are provided with an emergency power source and are required in shutting down the reactor to cold shutdown conditions or in mitigating the consequences of an accident. These pumps, which are installed in San Onofre, Units 2 and 3, are either centrifugal or displacement type pumps.

Section 3.9.6.2 discusses the program for inservice testing of ASME Class 1, 2 and 3 valves which are required to perform a specific function in shutting down a reactor to the cold shut down condition or in mitigating the consequences of an accident.

3.9.6.1 INSERVICE TESTING OF PUMPS The Inservice Testing Program for ASME Class 1, 2 and 3 pumps was developed in accordance with, and meets the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, 1977 Edition through Summer 1978 Addenda. Where these require ments were determined to be impractical, a specific request for relief was written and documented in Appendix A of the -same program. This Inservice Testing Program will remain in effect throughout the first 10 year inspection interval.

Identified-in Table 3.9-28 are those pumps which will undergo performance testing, along with the parameters to be measured. Each of these test para meters will be compared with a reference value of the same parameter, and deviations from this refer ence value will be evaluated against the ranges given in Table IWP-3100-2.

Presently, San Onofre Units 2 and 3 are still under construction, hence, the systems are not available for pump operation. When the pumps and associated systems are accepted under ASME Section III, then reference values will be established and documented in the FSAR prior to the first inservice pump test.

Station Operating Procedures will be developed prior to the preservice pump test to maintain consistent test methods, to identify reference values used, and to ensure proper system lineup before, during and after each pump test. The pump tests will be per formed every 3 months during normal plant operation.

Pumps that are operated more frequently than every months will not be run or stopped for a special test, provided the requirements of IWP-3400(b) are met.

The method of measurement specified in IWP-4000 will be used unless an alternative method which is demon strated to be equivalent or superior to those of the specified method is chosen.

3.9.6.2 INSERVICE TESTING OF VALVES The Inservice Testing Program for ASME Class 1, 2 and 3 valves was developed in accordance with, and meets the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV, 1977 Edition through Summer 1978 Addenda. Where these requirements were determined to be impractical, a specific request for relief was written and docu mented in Appendix B of the same program. This Inservice Testing Program will remain in effect throughout the first 10 year inspection interval.

Identified in Table 3.9-30 are those valves which will undergo performance testing, along with their Code class, valve category valve size and type.

Except for valves directly in the flow path (B Passive), valves exempt per IWV-1200 are not listed.

Station Operating Procedures will be developed prior to the preservice valve test, to maintain a consistent test method, to identify special test requirements, and to ensure proper system lineup before, during, and after each valve test.

SAN ONOFRE 2&3 FSAR MECHANICAL SYSTEMS AND COMPONENTS Table 3.9-30

SUMMARY

OF ASME CLASS 1, 2 AND 3 VALVES REQUIRING INSERVICE TESTING SYSTEM: Diesel Generators P&ID: 40110-5 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 2-001-D-145 2 -3 2" GA 2-003-D-145 2 B 2" GA 2-006-D-145 2 B 2" GA 2-011-D-145 2 B 2" GA SYSTEM: Reactor Coolant P&ID: 40111-6 PSV-0200 1 C 6" SV PSV-0201 1 C 6" SV 3-152-A-551 1 C 3" CK SYSTEM: Safety Injection P&ID: 40112-7 FV-0306 2 B 12" BALL HV-9300 2 B 24" GA HV-9301 2 B 24" GA HV-9302 2 A 24" BTF HV-9303 2 A 24" BTF HV-9304 2 A 24" BTF HV-9305 2 A 24" BTF HV-9316 2 B 12" BALL

SYSTEM: Safety Inje on (cont.) P&ID: 40112-7 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 2-034-C-329 2 C 2" SCK 2-035-C-329 2 C 2" SCK 2-036-C-329 2 C 2" SCK 2-037-C-329 2 C 2" SCK 2-063-C-329 2 C 2" SCK 2-104-C-329 2 C 2" SCK 3-155-C-329 2 C 3" CK 4-012-C-358 2 C 4" SCK 4-013-C-075 2 B 4" GA 4-014-C-075 2 B 4" GA 4-015-C-358 2 C 4" SCK 4-016-C-358 2 C 4" SCK 4-017-C-553 2 C 4" CK 8-007-C-212 2 B 8" GA 8-009-C-212 2 B 8" GA 8-010-C-212 2 B 8" GA 8-011-C-212 2 B 8" GA 10-006-C-675 2 C 10" CK 10-008-C-675 2' C 10" CK 10-024-C-406 2 C 10" SCK 10-025-C-406 2 C 10" SCK 12-038-C-173 2 B 12" GA 12-039-C-173 2 B 12" GA 14-015-C-173 2 B 14" GA 14-018-C-173 2 B 14" GA 14-078-C-173 2 B 14" GA 14-079-C-173 2 B 14" GA

SYSTEM: Safety Injel n (cont.) P&ID: 40112-7 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 14.080-C-173 2 B 14" GA 14-081-C-173 2 B 14" GA 14-082-C-173 2 B 14" GA 14-153-C-173 2 B 14" GA 16-005-C-212 2 B 16" GA 16-022-C-173 2 B 16" GA 16-023-C-173 2 B 16" GA 16-062-C-212 2 8 16" GA 16-077-C-645 2 C 16" CK 16-084-C-645 2 C 16" CK 24-001-C-724 2 C 24" SDCK 24-002-C-724 2 C 24" SDCK 24-003-C-724 2 C 24" SDCK 24-004-C-724 2 C 24" SOCK SYSTEM: Safety Injection P&ID: 40113-6 HV-9322 2 B 8" GL HV-9323 2 B .2" GL HV-9324. 2 B 2" GL HV-9325 2 B 8" GL HV-9326 2 B 2" GL HV-9327 2 B 2" GL HV-9328 2 B 8" GL HV-9329 2 B 2" GL HV-9330 2 B 2" GL HV-9331 2 B 8" GL HV-9332 2 B 2" GL

SYSTEM: Safety Inje on (cont.) W P&ID: 40113-6 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9333 2 B 2" GL HV-9334 2 A 2" GL HV-9336 2 A 16" GA HV-9337 1 A 16" GA HV-9339 I B 10" GA HV-9340 1 B 12" GA HV-9341 1 B 1" GL HV-9345 2 B 1" GL HV-9350 1 B 12" GA HV-9353 2 B 8" GA HV-9355 2 B 1" GL HV-9359 2 B 8" GA HV-9360 1 B 12" GA HV-9361 1 B 1" GL HV-9365 2 B 1" GL HV-9370 1 B 12" GA HV-9375 1 B 1" GL HV-9377 1 A 10" GA HV-9378 1 B 10" GA HV-9379 2 A 16" GA PSV-9349 2 C 8" RV 2-099-C-334 2 A 2" GL 3-018-A-551 1 C 3" CK 3-019-A-551 1 C 3" CK 3-020-A-551 1 C 3" CK 3-021-A-551 1 C 3" CK 3-156-A-551 1 C 3" CK

SYSTEM: Safety Injec n (cont.)

• P&ID: 40113-6 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 8-072-A-552 1 C 8" CK 8-073-A-552 1 C 8" CK 8-074-A-552 1 C 8" CK 8-075-A-552 1 C 8" CK 12-027-A-551 1 C 12" CK 12-029-A-551 1 C 12" CK 12-031-A-551 1 C 12" CK 12-033-A-551 1 C 12" CK 12-040-A-551 1 C 12" CK 12-041-A-551 1 C 12" CK 12-042-A-551 1 C 12" CK 12-043-A-551 1 C 12" CK SYSTEM: Containment Spray P&ID: 40114-6 FV-0318 2 B 2" GL FV-0328 2 B 2" GL HV-9306 2 B 4" GA.

HV-9307 2 B 4" GA HV-9347 2 B 4" GA HV-9348 2 B 4" GA HV-9367 2 A 8" GA HV-9368 2 A 8" GA HV-9398 2 B 2" GL HV-9399 2 B 2" GL HV-9420 2 A 3" GL HV-9433 1 B 1" GL HV-9434 2 A 3" GL.

SYSTEM: Containment ray (cont.) P&ID: 40114-6 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9437 1 B 1" GL 2-010-C-329 2 C 2" SCK 2-Ol1-C-329 2 C 2" SCK 2-050-C-376 2 B 2" GL 2-051-C-376 2 C 2" CK 2-052-C-376 2 B 2" GL 2-053-C-611 2 C 2" CK 2-054-C-611 2 C 2" CK 2-055-C-376 *2 B 2" GL 2-069-C-611 2 C 2" CK 3-066-A-050 1 B 3" GA 3-067-A-050 1 B 3" GA 3-157-A-551 1 AC 3" CK 3-158-A-551 1 AC 3" CK 8-003-C-173 2 B 8" GA 8-004-C-406 2 AC 8" SCK 8-005-C-173 2 B 8" GA 8-006-0-406 2 AC 8" SCK 8-012-C-406 2 C 8" SCK 8-014-C-406 2 C 8" SCK 12-001 C-173 2 B 12" GA 12-002-C-173 2 B 12" GA 16-087-C-675 2 C 16" CK 16-088-C-675 2 C 16" CK SYSTEM: Diesel Generator Fuel P&ID: 40116-7 Storage 2-039-0-627 3 C 2" CK

SYSTEM: Diesel GenE or Fuel Storage (cont.) P&ID: 40116-7 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 2-040-D-145 2 B 2" GA 2-041-D-145 2 B 2" GA 2-043-D-145 2 B 2" GA 2-044-D-145 2 B 2" GA 2-045-D-145 2 B 2" GA 2-047-D-145 2 B 2" GA 2-048-D-627 3 C 2" CK 2-049-D-145 2 B 2" GA 2-054-D-145 3 C 2" CK 2-055-D-145 2 B 2" GA 2-056-D-145 2 B 2" GA 2-058-D-145 2 B 2" GA 2-059-D-145 2 B 2" GA 2-060-D-145 2 B 2" GA 2-062-D-145 2 B 2" GA 2-063-D-627 3 C 2" CK 2-064-D-145 2 B 2" GA 3-052-D-221 2 B 3" GA 3-065-D-221 2 B 3" GA 3-067-D-221 2 B 3" GA 3-075-D-221 2 B 3" GA 3-076-D-221 2 B 3" GA Sumps & Drains P&ID: 40117-12 SYSTEM:

HV-5803 2 A 3" GA HV-5804 2 A 3" GA

SYSTEM: Fuel Pool

• ing P&ID: 40122-10 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HCV-7766 2 B 24" BTF HCV-7767 2 B 24" BTF 1-028-0-611 3 C 1" CK 6-067-C-212 2 B 6" GA 10-068-C-076 2 B 10" GA 10-100-C-212 2 A 10" GA 10-101-C-212 2 A 10" GA SYSTEM: Chemical & Volume Control P&ID: 40123-7 HV-9100 2 A 2" GA HV-9201 1 B 2" GA HV-9202 1 B 2" GA HV-9203 1 B 2" GA HV-9204 1 B 2" GA HV-9205 2 A 2" GL TV-0221 1 B 2" GL TV-9267 2 A 2" GA 2-019-A-554 1 C 2" CK 2-020-A-554 1 C 2" CK 2-021-A-554 1 C 2" CK 2-084-C-334 2 B 2" GL 2-091-C-334 2 B 2" GL 2-107-A-305 2 B 2" GL 2-122-C-554 2 AC 2" CK 3-092-C-105 2 B 3" GA SYSTEM: Chemical & Volume Control P&ID: 40124-6 HV-9217 2 A 3/4" GL

SYSTEM: Chemical & V me Control P&ID: 40124-6 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9218 2 A 3/4" GL LV-0227B 2 B 4" GA LV-0227C 2 B 4" GA 1 -094-C-611 2 C 1" CK 2-017-C-554 2 C 2" CK 2-018-C-334 2 B 2" GL 2-064,C-334 2 B 2" GL 2-067-C-554 2 C 2" CK 2-068-C-334 2 B 2" GL 2-069-C-554 2 C 2" CK 2-070-C-334 2 B 2" GL 3-053-C-675 2 C 3" CK 3-082-C-675 2 C 3" CK 3-083-C-675 2 C 3" CK 4-015-C-675 2 C 4" CK 4-016-C-212 2 B 4" GA 4-062-C-212 2 B 4" GA 4-063-C-212 2 B 4" GA 6-052-C-675 2 C 6" CK 6-054-C-212 2 B 6" GA SYSTEM: Chemical & Volume Control P&ID: 40125-6 FV-0210Y 3 B 1" GL HV-9231 3 B 2" GL HV-9236 3 B 2" GL HV-9235 3 B 3" GA HV-9240 3 B 3" GA

SYSTEM: Chemical &@lume Control (cont.) P&ID: 40125-6 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9247 3 B 3" GA HV-9257 3 B 1" GL

-043-D-885 2 B " NEEDLE

-045-C-611 2 C " CK 1-037-D-396 2 B 1" GL 1-038-D-396 2 B 1" GL 1-045-D-396 2 B 1" GL 1-047-D-396 2 B 1" GL 2-040-D-396 2 B 2" GL 2-042-D-396 2 B 2" GL 2-044-D-396 2 B 2" GL 3-004-D-212 2 B 3" GA 3-005-D-212 2 B 3" GA 3-006-D-212 2 B 3" GA 3-007-D-212 2 B 3" GA 3-033-D-675 3 C 3" CK 3-034-D-675 2 B 3" GA 3-035-D-675 3 C 3" CK 3-036-D-212 2 B 3" GA SYSTEM

Component Cooling Water P&ID: 40126-10 HCV-6215 2 B 28" BTF HCV-6510 2 B 30" BTF HCV-6511 2 B 28" BTF HCV-6512 2 B 30" BTF HCV-6513 2 B 1" GL HCV-6514 2 B 28" BTF

SYSTEM: Component CI )ing Water (cont.) P&ID: 40126-10 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HCV-6515 2 B 30" BTF HCV-6547 3 B 18" BTF HCV-6548 3 B 18" BTF HV-6200 3 B 30" BTF HV-6201 3 B 30" BTF HV-6202 3 B 30" BTF HV-6203 3 B 30" BTF HV-6211 2 A 10" BTF HV-6212 3 B 28" BTF HV-6213 3 B 28" BTF HV-6293B 3 B 8" BTF HV-6376 3 B 1" GA HV-6377 3 B 1" GA HV-6378 3 B 1" GA HV-6379 3 B 1" GA HV-6494 2 B 30" BTF HV-6495 3 B 30" BTF HV-6496 2 B 30" BTF HV-6497 3 B 30" BTF HV-6522B 3 B 8" BTF 1-013-D-691 3 C 1" CK 1-014-9-805 2 B 1" BALL 1-015-D-805 2 B 1" BALL 1-016-D-691 3 C 1" CK 1-019-D-805 2 B 1" BALL 1-020-D-805 2 B 1" BALL 1-021-D-691 3 C 1" CK

SYSTEM: Component C ing Water (cont.) P&ID: 40126-10 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 1-022-D-805 2 B 1" BALL 1-024-D-691 3 C 1" CK 1-027-D-805 2 B 1" BALL 1-028-D-805 2 B 1" BALL 1-031-D-805 3 C 1" BALL 1-032-0-805 2 B 1" BALL 1-033-D-805 2 B 1" BALL 1-034-D-805 2 B 1" BALL 029-D-691 3 C 1" CK 1;-030-D-691 3 C 11" CK 11-226-D-387 3 B 1" GL 1 -227-D-387 3 B 1 " GL 11-229-D-387 3 B 1 " GL 1 -230-D-387 3 B 1 " GL 2-228-D-387 3 B 2" GL 2-236-D-387 3 B 2" GL 2-258-D-387 3 B 2" GL 2-259-D-387 3 B 2" GL 3-014-0-221 3 B 3" GA 3-015-D-221 3 B 3" GA 12-002-D-221 2 B 12" GA 30-009-D-722 3 C 30" SDCK 30-010-D-722 3 C 30" SDCK 30-011-0-722 3 C 30" SDCK 30-012-D-722 3 C 30" SDCK

SYSTEM: Component ling Water P&ID: 40127-9 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HCV-6507 2 B 28" BTF HCV-6520 2 B 28" BTF HCV-6521 2 B 28" BTF HCV-6537 3 B 10" BTF HCV-6538 3 B 10" BTF HCV-6539 3 B 10" BTF HV-6216 2 A 10" BTF HV-6218 3 B 28" BTF HV-6219 3 B 28" BTF HV-6221 2 B 10" BTF HV-6222A 2 B 28" BTF HV-6222B 2 B 28" BTF HV-6224A 2 B 28" BTF HV-6224B 2 B 28" BTF HV-6225 2 B 6" GA HV-6227 2 B 3" GA HV-6229 2 B 3" GA HV-6293A 3 B 8" BTF HV-6500 3 B 18" BTF HV-6501 3 B 18" BTF HV-6505 2 B 6" GA HV-6522A 3 B 8" BTF HV-6551 2 B 10" BTF HV-6552 2 B 10" BTF 1-265-D-627 3 C 1" CK 1-267-0-627 3 C 1" CK.

2-108-D-387 2 B 2" GL

SYSTEM: Component ling Water (cont.) P&ID: 40127-9 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 3-268-D,681 3 C 3" CK 3-269-D-681 3 C 3" CK 28-101-D-725 3 C 28" SDCK 28-102-D-725 3 C 28" SDCK 28-103-D-725 3 C 28" SDCK SYSTEM: Nuclear Sampling P&ID: 40128-7 HV-0508 2 A 3/4" GL HV-0509 2 A 3/4" GL HV-0510 2 A 3/4" GL HV-0511 2 A 3/4" GL HV-0512 2 A 3/4" GL HV-0513 2 A 3/4" GL HV-0514 2 A 3/4" GL HV-0515 2 A 3/4" GL HV-0516 2 A 3/4" GL HV-0517 2 A 3/4" GL 3-003-C-335 2 B 1/2" GL 3-010-C-335 2 B 1/2" GL SYSTEM: Coolant Radwaste P&ID: 40131-9 HV-7512 2 A 3" GL HV-7513 2 A 3" GL

SYSTEM: Coolant a oric Acid Recycle P&ID: 40133-8 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 2-321-C-376 2 A 2" GL 2-573-C-611 2 AC 2" CK SYSTEM: Waste Gas System P&ID: 40135-8 HV-7258 2 A 3" GA HV-7259 2 A 3" GA SYSTEM: Nuclear Service Water P&ID: 40140-12 HV-7911 2 A 3" GA 3-236-C-675 2 AC 3" CK SYSTEM: Main Steam P&ID: 40141-9 HV-4053 2 B 6" GL HV-4054 2 B 6" GL HV-4057 2 B 3/4" GL HV-4058 2 B 3/4" GL HV-8200 2 B 4" GL HV-8201 2 B 4" GL HV-8202 2 B 4" GL HV-8203 2 B 4" GL HV-8204 2 B 40" GA HV-8205 2 B 40" GA HV-8248 2 B 1" GA HV-8249 2 B 1" GA

.HV-8419 2 B 8" RV HV-8421 2 B 8" RV PSV-8401 2 C 6" SV

SYSTEM: Main Steam (t.) P&ID: 40141-9 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE PSV-8402 2 C 6" SV PSV-8403 2 C 6" SV PSV-8404 2 C 6" SV PSV-8405 2 C 6" SV PSV-8406 2 C 6" SV PSV-8407 2 C 6" SV PSV-8408 2 C 6" SV PSV-8409 2 C 6" SV PSV-8410 2 C 6" SV PSV-8411 2 C 6" SV PSV-8412 2 C 6" SV PSV-8413 2 C 6" SV PSV-8414 2 C 6" SV PSV-8415 2 C 6" SV PSV-8416 2 C 6" SV PSV-8417 2 C 6" SV PSV-8418 2 C 6" SV 4-003-D-620 3 C 4" CK 4-005-D-620 3 C 4" CK 6-124-C-599 2 C 6" CK 6-448-C-599 2 C 6" CK 8-001-C-129 2 B 8" GA 8-231-C-129 2 B 8" GA 20-036-C-609 2 C 20" CK 20-129-C-609 2 C 20" CK

SYSTEM: Condensate A s P&ID: 40150-12 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 8-471-D-212 3 B 8" GA 8-473-D-212 3 B 8" GA SYSTEM: High Pressure & Auxiliary Feedwater P&ID: 40156-8 HV-4048 2 B 20" GA HV-4052 2 B 20" GA HV-4705 3 B 6" GA HV-4706 3 B 6" GA HV-4712 3 B 4" GL HV-4713 3 B 4"9 GL HV-4714 2 B 6'" GA HV-4715 2 B 6" GA HV-4716 3 B 4" GA HV-4730 2 B 6" GA HV-4731 2 B 6" GA 3-496-D-617 3 C " CK

-497-D-617 3 C " CK 1-498-D-617 3 C " CK

-499-D-617 3 C " CK 6-121-D-598 3 C 6" CK 6-122-D-087 2 B 6" GA 6-123-0-087 2 B 6" GA 6-125-D-087 2 B 6" GA 6-126-0-598 3 C 6" CK 6-127-D-087 3 B 6" GA 6-128-D-087 2 B 6" GA 6-130-D-087 2 B 6" GA

SYSTEM: High Pressunr Auxiliary Feedwater (cont.)

• P&ID: 40156-8 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 6-131-D-087 2 B 6"1 GA 6-133-D-087 2 B 6" GA 6-134-0-087 2 B 6" GA 6-136-D-087 2 B 6" GA 8-468-D-212 3 B 8" GA 8-469-D-212 3 B 8" GA SYSTEM: Auxiliary Boiler P&ID: 40169-9 2-037-C-387 2 A 2" GA 2-038-C,387 2 A 2 GA SYSTEM: HV & AC (Normal) P&ID: 40170-8 HV-7800 2 A 3/4" GA HV-7801 2 A 3/4 GA HV-7802 2 A 3/4" GA HV-7803 2 A 3/4"' GA HV-7805 2 A 3/4" GA HV-7806 2 A 3/4" GA HV-7810 2 A 3/4" GA HV-7811 2 A 3/4" GA HV-9900 2 A 8" BTF HV-9920 2 A 8" BTF HV-9921 2 A 8" BTF HV-9971 2 A 8" BTF SYSTEM: HV & AC (Normal) P&ID: 40171-10 HV-9821 2 A 8" BTF

SYSTEM: HV & AC (No*) (cont.) . P&ID: 40171-10 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9823 2 A 8" BTF HV-9824 2 A 8" BTF HV-9825 2 A 8" BTF HV-9907AA 3 B 3" GA HV-9907AC 3 B 3" GA HV-9907BA 3 B 3" GA HV-9907BC 3 B 3" GA HV-9948 2 A 42" BTF HV-9949 2 A 42" BTF HV-9950 2 A 42" BTF HV-9951 2 A 42" BTF SYSTEM: HV & AC (Emergency) P&ID: 40172-9 HV 0500 2 A 1" GA HV-0501 2 A 1" GA HV-0502 2 A 1" GA HV-0503 2 A 1" GA HV,6366 2 A 10" GA HV-6367 2 A 10" GA HV-6368 2 A 10" GA HV-6369 2 A 10" GA HV,6370 2 A 10" GA HV-6371 2 A 10" GA HV-6372 2 A 10" GA HV-6373 2 A 10" GA HV-9917 2 A 6" BTF HV-9918 2 A 6" BTF

SYSTEM: HV & AC (Em ency) (cont.) P&ID: 40172-9 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE HV-9945 2 A 6" BTF HV-9946 2 A 6" BTF 10-203-C-221 2 B 10" GA 10-204-C-221 2 B 10" GA 10-205-C-221 2 B 10" GA 10-206-C-221 2 B 10" GA 10-207C-221 2 B 10" GA 10-208-C-221 2 B 10" GA 10-209-C-221 2 B 10" GA 10-210-C-221 2 B 10" GA SYSTEM: Auxiliary Building Emergency Chilled Water P&ID: 40179-10

-396-D-387 3 B " GL k,397-D,387 3 B " GL 1;1674-D-145 3 B 1" GA 1;-675-D-195 3 B 1" GA 4-672=D-221 3 B 4" GA 4-673-0-221 3 B 4" GA 8-001-D-801 3 B 8" BALL 8-003-D-801 3 B 8" BALL 8-185-0-801 3 B 8" BALL 8-186-D-801 3 B 8" BALL 8-385-D-801 3 B 8" BALL 8-389-D-801 3 B 8" BALL 8-301-n-801 3 B 8" BALL

SYSTEM: Auxiliary B10ding Emergency Chilled Water U P&ID: 40180-10 VALVE VALVE NUMBER CODE CLASS CATEGORY VALVE SIZE VALVE TYPE 1 -224-D-387 3 B 1 " GL 1 -225-D-387 3 B 1" GL 1 -678-D-145 3 B 1" GA 1;-679-D-145 3 B 1 GA 4-676-D-221 3 B 4" GA 4-677-D-221 3 B 4" GA 8-007-D-801 3 B 8" BALL 8-058-D-801 3 B 8" BALL 8-063-D-801 3 B 8" BALL 8-180-D-801 3 B 8" BALL 8-181-D-801 3 B 8" BALL 8-243-D-801 3 B 8" BALL SYSTEM: Fire Protection P&ID: 40184-9 HV-5686 2 A 4" GA 4-061-C-681 2 AC 4" CK

O ENCLOSURE 2 SONGS 2/3 FSAR 5.2.4 INSERVICE INSPECTION OF REACTOR COOLANT PRESSURE BOUNDARY COMPONENTS 5.2.4.1 Preservice Examination On October 18, 1973, San Onofre Units 2 and 3 were issued a construction permit for the two 1100 MWe pressurized water reactors. Relating this date to the requirements of 10CFR50.55a(g),

the Preservice Examination (PSE) Program shall comply, as a minimum, to ASME Section XI, 1971 Edition through Summer 1972 Addenda. To mini mize a change in scope between the preservice and inservice requirements, Southern California Edison upgraded the PSE Program to comply with the 1974 Edition through Summer 1975 Addenda.

Where these requirements were deemed to be im practical a specific relief was written and docu mented in Appendix A of the Preservice Inspection Program plan. This plan was developed and sub mitted to the NRC for review in September 1980.

5.2.4.2 Inservice Inspection San Onofre, Units 2 and 3 Inservice Inspection (ISI) Programs will comply, as a minimum, to the requirements of the latest edition and addenda of ASME Section XI which is incorporated by reference in paragraph (b).of 10CFR50.55a, twelve (12) months prior to the date of issuance of the license to operate at full power. Throughout the service life of San Onofre Units 2 and 3; com ponents (including their supports) will meet these requirements, except for desig.n and access'pro visions, to the extent practical within the limi tations of design, geometry, and materials of con struction of the component.

The ISI Program will be submitted for review six months before the start of our initial 120 month inspection interval per IWA-2400(b) so that compliance with 10CFR50.55a(g) can be demonstrated.

Included in the ISI Program will be those except ions taken during the preservice examination.

-1.-

5.2.4.3 System Boundary Subject to Inspection San Onofre Units 2 and 3 ISI Program was developed to ASME Section XI, 1977 Edition through Summer 1978 Addenda and the system boundaries for Class 1 pressure retaining components (and their supports) were developed to the requirements of 10CFR5 0.2, paragraph (v).

The ISI Program includes those limitations and modifications required of 10CFR50.55a(g) and iden tified in the October 9, 1979 Federal Register, Volume 44, No. 196.

5.2.4.4 Accessibility Access to examine Class 1 pressure retaining com ponents, (and their supports) has been provided to accommodate either manual or mechanized devices as warranted by the environment or location of the weld. Based on the preservice examination activi ties, this design provides adequate access to com ponents, therefore, exception to the rules of ASME Section XI is not required.

Provisions were incorporated into San Onofre Units 2 and 3 design to accommodate removal and storage of structural members, shielding components, and insulating material to permit access to Class 1 components being examined. Hoists or other handling machinery needed to manipulate these structural .

members, shielding components, etc. were also pro vided.

5.2.4.4.1 Remote Examination During San Onofre Units 2 and 3 lifetime, radiation fields may increase in some areas. To minimize examination personnel exposure in these select areas, remote examination equipment is utilized. The below described equipment was utilized once during the preservice examination to demonstrate its performance.

The reactor shell welds, nozzle-to-shell welds, and nozzle inner radius sections are examined by means of the PaR Model ISI-2 positioning device. This device which is mounted on the flange of the vessel, positions the search unit fixtures within the vessel. An electric hoist atop the PaR mast provides the vertical move ment along the vessel centerline by actu ating a multisection telescoping tube. An SONGS 2/3 FSAR inspection boom is mounted at the bottom of the telescoping tube and can be rotated through 3600 by means of an electric motor. The end of the boom is extended outward by a hydraulic mechamism.

At the end of the boom is a rotator upon which the various UT examination devices are mounted. In this way, complete flexi bility of motion is provided to carry out the required Code examinations. The con trol console of the PaR device contains digital readouts for the hoist, rotation, and extension motions, and the control module for the rotator contains a digital readout for its rotational position.

An ID examination of the reactor vessel nozzle-to-shell welds is performed using the shell side nozzle scanner. This scanner is mounted on the end of the PaR boom and is aligned on each nozzle center line by means of the PaR controls. It is rotated about the nozzle centerline by the rotator on the end of the PaR boom and has an independent mechanism for radial motion which is controlled by the data acquisition system. Pro vision is also made for keeping the search units in contact with the vessel wall as the fixture is rotated around the compound curvature of the vessel ID.

The flange-to-shell weld and the flange ligament areas of the reactor pressure vessel will be examined from the top' surface of the reactor vessel flange utilizing remote mechanized equipment that consists of a track mounted on a frame concentric with and slightly larger than the stud hole circle. The track is slightly larger than one quan drant and is supported and located by alignment pins in stud holes beyond the examination area and by a trusswork extending away from the vessel. A carriage is moved along the track carry ing either a three transducer search unit along the closure mating surface to ex amine the flange weld or a single trans ducer search unit that could be rotated around each stud hole to examine the liga ment areas.

SONGS 2/3 FSAR Both the flange examination device and the PaR device operate in conjunction with the nuclear reflectoscope and the data acqui sition system which is an instrument pack age containing five multiplexed.UT channels and common control, data acquisition, and printing systems. Each channel can oper ate one UT transducer, meaning that up to five.different transducers giving five different examinations can be run simul taneously.

For the flange ligament and flange weld ex aminations, the carriage mechanisms are controlled automatically by the nuclear reflectoscope. For the vessel shell ex aminations, the PaR device is controlled manually and the positional information is fed electronically into the nuclear reflectoscope for use in triggering and printing. The examination too' used for the-examinations of the nozzle welds from the vessel shell side is controlled from both the PaR control panel and the nuclear reflectoscope.

5.2.4.5. Examination Techniques and Procedures San Onofre Units 2 and 3 ISI Program stipulates that the methods used for examination of Class 1 components are to be in accordance with ASME Section XI, Sub article IWA-2200.

All visual examinations are conducted to the require ments or IWA-2210 and this technique is used to de termine the general surface condition of a part or component.

All surface examinations are conducted to the re quirements of IWA-2200 and these techniques are used on dry surfaces to detect the presence of surface or near surface cracks or discontinuities.

All volumetric examinations are conducted to the re quirements of IWA-2230 and these techniques are used to detect the presence of subsurface indications.

If any alternative examination methods, combination of methods, or newly developed techniques are sub stituted for the above-described methods, results will be provided which demonstrate equivalence or superiority.

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SONGS Z/3 FSAR 5.2.4.6 Inspection Interval The inservice inspection program was developed to the schedule of IWB-2412, Inspection Program B, and will be performed during normal plant outages such as refueling shutdowns or maintenance shut downs during the inspection interval. All re quired examination will be completed during each 10 year interval with the exception of those examinations that may be deferred until the end of the inspection interval, all required examin ations will be distributed over the interval in accordance with Table IWB-2412-1.

5.2.4.7 Examination Categories and Requirements The requirements for the first inspection interval of San Onofre Units 2 and 3 Inservice Inspection Program is described both in the following para graphs and in Section 4.0.5 of San Onofre's Technical Specification. Except for the Steam Generators which are covered in Section 5.4.2.4.2, each com ponent is discussed by categories corresponding to ASME.Section XI, 1977 Edition through Summer 1978 Addenda.

5.2.4.7.1 Examination Category B-A, Pressure Retaining Welds 'in Reactor Vessel A. Reactor Vessel - Items B1.11 thru Bl.51 Welds in the reactor vessel shell will-be volumetrically examined using remote oper ated equipment. Except for Item B1.40, the examination of these vessel welds will require removal of the reactor in ternals and core barrel and where per missable, will be scheduled for perfor mance at the end of the inspection interval.

Item 1.30 will be volumetrically examined from both the flange mating surface and the reactor vessel inside surface using remote operated equipment.

.Item 1.40 and other welds in the closure head will be volumetrically examined using manual techniques. In addition, the closure head flex area will also receive a visual examination.

The extent of weld examined for Items B1.11 through B1.51 will cover essentially 100%

of the weld length.

SONGS 2/3 FSAR 5.2.4.7.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels A. Pressurizer - Items B2.10 thru B2.22 The pressurizer shell and head welds will be volumetrically examined using manual techniques.

The extent of weld examined will cover essentially lU0% of the weld length, except for item B2.12, which will only cover one foot of weld. The weld selected for item B2.12, will be that weld intersecting the circumferential shell-to-head weld examined.

5.2.4.7.3 Examination Category B-D,Full Penetration Welds of Nozzles in Vessels - Inspection Program B A. Reactor Vessel - Items B3.90 and B3.100 The reactor vessel nozzle-to-vessel weld and nozzle inside radius section on all six (b) nozzles will be volumetrically examined from the inside surface using remote operated equipment. The two outlet nozzles, or 33% of the nozzles,will be examined by the end of the first inspection period. The four inlet nozzles will be examined at the end of the inspection interval, since the core barrel needs removal for access.

The extent of weld examined for items B3.90 and B3.100 includes the nozzle-to-vessel weld and adjacent areas of the nozzle and reactor vessel for each of the six nozzles.

B. Pressurizer - Items B3.110 and B3.120 The pressurizer nozzle-to-vessel welds and nozzle inside radius section on the surge, spray and three safety nozzles will be volumetrically examined from the outside,,manually. All pressurizer instrument connections are excluded from volumetric examination per IWB-1220 (b)

The extent of weld examined for items B3.110 and B3.120 includes the nozzle-to-vessel weld and adjacent areas of the nozzle and pressurizer for each of the five nozzles.

5.2.4.7.4 Examination Category B-E, Pressure Retaining Partial Panetration Welds in Vessels

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SONGS 2/3 FSARD A. Reactor Vessel - Items B4.12 thru B4.14 Included in the partial penetration weld category are 91 control element -drive mechanism penetrations, 10 instrument penetrations and one reactor vessel closure head vent penetration. During each inspection interval, the examinations will cumulatively cover 25% of each group of penetrations of comparable size and function. Each of these selected penetrations will receive a visual examination where the system boundary is subjected to pressure testing.

B. Pressurizer - Item B4.20 Comprising the partial penetration weld category are thirty pressurizer heater connections, all of which are accessible for examination.

During each inspection interval the examinations will cumulatively cover 25% ol the total penetrations.

Each of the-selected pressurizer heater connec tions will receive a visual examination when the system boundary is subjected to pressure testing.

5.2.4.7.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds A. Reactor Vessel - Item B5.10 There are no dissimilar metal welds associated with San Onofre Units 2 and 3 reactor vessel.

Both the primary piping and the reactor vessel are constructed of ferritic material clad with stainless steel. The welds joining the reactor vessel nozzle to a transition piece and the transition piece to the primary piping is covered in Category B-J.

B. Pressurizer - Item B5.20 In total, there are five dissimilar metal welds which individually join the surge nozzle, spray nozzle and three safety nozzles with their respective piping. Each of these five welds will manually receive a surface and volumetric examination within the first inspection interval.

C. Piping - Item B5.50 There are 29 dissimilar metal welds within San Onofre Units 2 and 3 Class 1 piping systems.

In the reactor coolant piping the only large diameter dissimilar metal welds are those con SO1GS 2/3 FSAR necting up to the reactor coolant pump suction and discharge. Other smaller diameter dissimilar metal welds occur in piping runs such as the surge line, safety injection lines, etc.

Each of these 29 welds will receive a surface and volumetric examination within the first inspection interval.

5.2.4.7.6 -Examination Category B-G-1, Pressure Retaining Bolting, Larger than 2 inches .(51 mm) in diameter.

A. Reactor Vessel --Items B6.10 thru B6.50 Within the first inspection interval and upon disassembly of the closure head from the reactor vessel, the 54 closure studs, the 54 closure nuts, the 54 closure washers, and the ligaments between the 54 stud holes will be examined. Each closure stud and ligament between stud holes will manually receive a volumetric examination.

Each closure stud and closure nut will manually receive a surface examination. Each closure washer and the threads in each stud hole will manually receive a visual examination.

B. Pressurizer'- Items B6.60 thru B6.80 There is no bolting on San Onofre Units 2 and 3 pressurizers which exceeds 2 inches in diameter.

C. Piping - Items B6.150 thru B6.170 There is no bolting on San Onofre Units 2 and.3 piping which exceeds 2 inches in diameter.

D. Pumps - Items B6.180 thru B6.20u Upon disassembly of the reactor coolant pump for maintenance, the bolts and studs which are removed will manually receive a surface and volumetric examination. The nuts, washers, threads in .base material, and ligaments between threaded stud holes will manually receive a visual examination.

When the main coolant pump is not disassembled within an inspection interval, a volumetric examination will manually be performed on the bolts and stud and a visual examination will be performed on the bolting.

SONGS 2/3 FSAR E. Valves - Items B6.210 thru B6.230 There is no bolting on San Onofre Units 2 and 3 valves which exceeds 2 inches in diameter.

5.2.4.7.7 Examination Category B-G-2, Pressure Retaining Bolting, 2 inches (51mm) and Smaller in Diameter A. Reactor Vessel' - Item B7.10 There is no bolting on San Onofre Units 2 and 3 reactor vessel which is 2 inches and smaller in diameter.

B. Pressurizer - Item B7.20 Twenty studs and twenty nuts on the pressurizer manway cover will be visually examined in place.

All twenty studs and twenty nuts will be examined within the first inspection interval.

C. Piping - Item B7.50 Safety valve-to-flange pipe connection bolting,and flanged pipe connections at flow meter orifices will be visually examined in place. All required bolting will be examined within the first inspection interval.

D. Pumps - Item B7.60 The reactor coolant pump seal-assembly bolting will be visually examined in place. All required bolting will be examined within the first inspec tion interval.

E. Valves - Item B7.70 All valve bonnet bolting will be visually examined in-place and within the first inspection interval.

5.2.4.7.8 Examinatin Category B-H, Vessel Supports A. Reactor Vessel - Item B8.10 Vessel supports for San Onofre Units 2 and 3 reactor vessels consists of four pads integral with the cold leg nozzles. ASME Section XI excludes integral support pads on nozzles from examination.

The four shear keys on the lower head will recieve a surface examination.

SONGS 2/3 FSAR B. Pressurizer - ItemB8.20 The pressurizer is supported on a skirt integrally welded to the bottom head of the pressurizer. A surface examination will be performed on essentially 100% of the length of the weld and 1/2 inch on either side of the weld.

5.2.4.7.9 Examination Category B-J, Pressure Retaining Welds in Piping Per 10CFR50.55a (g) rules, SCE optionally selects to perform inservice inspection on Class 1 piping to the rules of ASME Section XI, 1974 Edition through Summer 1975 Addenda.

A. Piping - Items B4.5 thru B4.8 During each inspection interval, 25% of the total number of circumferential pipe welds and 12 inches of each adjoining longitudinal weld intersecting the circumferential welds will undergo a volumetric examination. In addition, 25% of the total number of branch pipe connection welds exceeding 6 inches in diameter will also undergo a volumetric exam ination.

Branch pipe connection welds, 6 inches in dia meter and smaller and socket welds will receive a surface examination.

5.2.4.7.10 Examination Category B-K-1, Support Members for Piping, Pumps and Valves A. Piping - Item B10.10 Integral attachments welded to the pressure boundary will receive a surface examination on essentially 100% of the weld length. Those supports not associated with piping required to be examined by Examination Category B-J or whose support base material design thickness is less than 5/8 of an inch will be excluded from examination.

B. Pumps - Item B10.20 Each of the four reactor coolant pumps are supported by a separate support skirt which is welded to the pump casing. The configuration of SONGS 2/3 FSAR these supports severly limits access to the inside of the supports for surface examination. During the first inspection in terval, each of the four supports will be examined by the surface method to the extent practicable.

C. Valves - Item B10.30 There are fifteen integrally welded supports for Class 1 valves. Each of these attachment welds will receive a-surface examination during the first inspection interval.

5.2.4.7.11 Examination Category B-K-2, Component Supports for Piping, Pumps, and Valves A. Piping - Item B11.10 All component supports for piping will be visually examined from the component up to and including the attachment to the supporting structure, during the first inspection interval. Also included will be a verification of the settings of constant and variable spring type hangers, snubbers, and shock absorbers.

B. Pump - Item B11.20 All component supports for the reactor coolant pump will be viaually examined from the component up to and including the attachment to the supporting structure, during the first inspection interval. Also included will be a verification of the settings of constant and variable spring type hangers, snubbers, and shock absorbers.

C. Valves - Item B11.30 All component supports for Class 1 valves will be visually examined from the component up to and including the attachment to the support structure, during the first inspection interval. Also in cluded will be a verification of the settings of constant and variable spring-type hangers, snubbers, and shock absorbers.

5.2.4.7.12 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings A. Pumps - Item B12.10 The reactor coolant-pump casings are manufactured

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SONGS 2/3 FSAR using cast stainless steel material and contain a pressure retaining weld. Meaningful examinations cannot be per formed on these welds utilizing currently available com mercial ultrasonic equipment. If practicable, one pump will be gamma-radiographed at the end of the first inspection interval. During the preservice examination these welds have been radiographed and were examined physcially prior to final assembly of the pumps.

5.2.4.7.13 Examination Category B-L-2, Pump Casings A. Pumps - Item B12.20 The internal pressure boundary surfaces of the reactor coolant pumps are normally not accessible. If maintenance on the pump is required during the first inspection interval, a visual examination of the pump internals will be per formed on the accessible surfaces.

5.2.4.7.14 Examination Category B-M-1, Pressure Retaining Welds in Valve Bodies A. Valves - Item B12.30 Seven valve bodies are manufactured using cast stainless steel material and contain pressure retaining welds. By utilizing currently available commercial ultrasonic equip ment, meaningful examinations cannot be performed. However, these welds have.been radiographed and were examined visually during the preservice examination phase.. Since these valves are of the same design, perform the same function, and were fabricated by the same manufacturer, one valve, if practical, will be gamma radiographed by the end of the first inspection interval.

5.2.4.7.15 Examination Category B-M-2, Valve Bodies A. Valves - Item B12.40 When a valve is disassembled for normal maintenance the internal pressure boundary surface will be visually examined in the first inspection interval. This examin ation pertains to valves exceeding 4-inch nominal pipe size in each group of valves of the same constructional design.

5.2.4.7.16 Examination Category B-N-1, Interior of Reactor Vessel A. Reactor Vessel - Item B13.10

SONGS 2/3 FSARM A remote visual examination will be conducted on the reactor vessel interior surfaces, both above and below the reactor core, that is made accessible for examination by removal of com ponents during normal refueling outages. This examination will be conducted at the first refueling outage and subsequent refueling outages at approximately 3-year intervals.

5.2.4.7.17 Examination Category B-N-2, Integrally Welded Core Support Structures and Interior Attachments to Reactor Vessels A. Reactor'Vessel - Items B13.20 and B13.21 Not Applicable to Pressurized Water Reactors.

5.2.4.7.18 Examination Category B-N-3, Removable Core Support Structures A. Reactor Vessel - Item B13.30 All accessible attachment welds and accessible surfaces of the core support structure will be visually examined when the core support structure is removed from the reactor vessel. This examina tion will be performed at the end of the first inspection interval.

5.2.4.7.19 Examination Category B-0, Pressure Retaining Welds in Control Rod Housings A. Reactor Vessel - Item B14.10 The control rod drive housing weld metal and base metal for 1/2 inch beyond the edge of the weld will be examined manually. During the first inspection interval, 100% of the welds in 10%

of the peripheral control element drive mechan ism housings will have a surface examination performed on them.

5.2.4.7.20 Examination Category B-P, All Pressure Retaining Components A. Reactor Vessel - Items B15.10 and B15.11 During the system pressure test, which is conducted each refueling, a visual examination will be conducted for evidence of leakage to the rules of IWA-5000 and IWB-5000.

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SONGS 2/3 FSAR During the system hydrostatic test, which is normally conducted once each inspection interval, a visual examination will be con ducted for evidence of leakage to the rules of IWA-5000 and IWB-5000.

B. Pressurizer - Items B15.20 and B15.21 Same examination as specified in (A)

C. Piping - Items B15.50 and B15.51 Same examination as specified in (A)

D. Pumps - Items B15.60 and B15.61 Same examination as specified in (A)

E. Valves - Items B15.70 and B15.71 Same examination as specified in (A) 5.2.4.8 Evaluation of Examination Results In the conduct of San Onofre's inservice examination all indications which are required to be evaluated are done so to the acceptance standards of IWB-3000.

If further evaluation is required the rules of ASME Section XI, Appendix A may also be utilized. Where the indication requires a repair on the component, these repairs will be conducted to the rules of IWA,'4000 and IWB-4000.

5.2.4.9 System Leakage and Rydrostatic Pressure Tests As indicated in Section 5.2.4.7.20, all pressure re taining components receive a system leakage test each refueling and a system hydrostatic test once each in spection interval.

All pressure tests will be conducted to the pressure temperature requirements stated in the Technical Specification.

5.2.4.10 Reactor Coolant Pump Flywheel The reactor coolant pump flywheel assemblies will be examined in place consistent with the recommendations of NRC Regulatory Guide 1.14 (Revision 0).

ENCLOSURE 3 SONGS 2/3 FSAR SECTION 5.4.2.4.2 STEAM GENERATOR INSERVICE INSPECTION 5.4.2.4.2.1 Preservice Examination As stated in Subsection 5.2.4, the preservice examin ation for Class 1 steam generator components complies with the requirements of ASME Section XI, 1974 Edition through Summer 1975 Addenda. Where these requirements were deemed to be impractical a specific request for relief was written and documented in Appendix A of the Preservice Inspection Program plan. This plan was de veloped and submitted to the NRC for review in September 1980.

The Preservice and Inservice Inspection Programs for examining steam generator tubes are consistent with the recommendation of NRC Regulatory Guide 1.83, Revision

1. The preservice examination requirements for steam generator tube inspection have been adequately met and all unacceptable defects were eliminated in accordance with ASME Section III.

5.4.2.4.2.2 Inservice Inspection San Onofre, Units 2 and 3 Inservice Inspection (ISI) for Class 1 steam generators will comply, as a minimum, to the requirements of the latest edition and addenda of ASME Section XI which is incorporated by reference in paragraph (b) of 10CFR50.55a, twelve (12) months prior to the date of issuance of the license to operate at full power.

The ISI Program which includes information on steam generators will be submitted for review six months before the start of our initial 120 month inspec tion interval per IWA-2400(b) so that compliance with 10CFR50.55(g) can be demonstrated. Included in the ISI Program will be those exceptions taken during the preservice examination.

5.4.2.4.2.3 System Boundaries Subject to Inspection San Onofre Units 2 and 3 ISI Program is being developed to ASME Section XI, 1977 Edition through Summer 1978 Addenda and the system boundaries for Class 1 pressure retaining components (and their supports) were developed to the requirements of 10CFR50.2, paragraph (v).

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5.4.2.4.2.4 Accessibility Access to examine the primary side of the steam gen erators has been provided to accommodate either manual or mechanized devices as warranted by the environment or location of the weld. This design provides adequate access to components, therefore, exception to the rules of ASME Section XI is not required.

Provisions were incorporated into San Onofre Units 2 and 3 design to accommodate removal and -storage of structural members, shielding components, and insulat ing material to permit access to the Class 1 steam generators being examined. Hoists or other handling machinery needed to manipulate these structural mem bers, shielding components, etc. were also provided.

The design of San Onofre Units 2 and 3 steam gener ators allows access for examination of individual tubes, access for inspection and plugging personnelamd provisions for ensuring that personnel radiation ex posure is maintained as low as practicable.

During San Onofre Units 2 and 3 lifetime, radiation fields may increase in some areas. To minimize exam ination personnel exposure in these select areas, remote examination equipment is utilized. The below described equipment was utilized once during the pre service examination, to demonstrate its performance.

For steam generator stay weld examinations a.' free standing track section is mounted vertically in the center of the steam generator stay cylinder. The bottom of the track is attached to the top of the steam generator sliding base. A remote scanner is installed on the vertical track whenever examinations are performed. The scanner consists of a motor-driven vertical carriage-with a platform that can rotate 3600.

A telescoping radial arm is mounted on the rotating platform, and the ultrasonic search units are mounted on the end of this arm. All motions are controlled by the automatic control system previously described in paragraph 5.2.4.1.

5.4.2.4.2.5 Examination Techn4Iques and Procedures San Onofre Units 2 and 3 ISI Program stipulates that the methods used for examination of Class 1 components are to be in accordance with ASME Section XI, Sub article IWA-2200.

All visual examinations are conducted to the require ments of IWA-2210 and this technique is used to deter mine the general surface condition of a part or com ponent.

All surface examinations are conducted to the require ments of IWA-2220 and these techniques are used on dry surfaces to detect the presence of surface or near surface cracks or discontinuities.

All volumetric examinations are conducted to the re quirements of IWA-2230 and these techniques are used to detect the presence of subsurface indications.

If any alternative examination methods, combination of methods, or newly developed techniques are sub stituted for the above described methods, results will be provided which demonstrate equivalence or superi ority.

5.4.2.4.2.6 Inspection Interval The inservice inspection program was developed to the schedule of IWB-2412, Inspection Program B, and will be performed during normal plant outages such as re fueling shutdowns or maintenance shutdowns occuring during the inspection interval. Except for those ex aminations that may be deferred until the end of the inspection interval, all required examinations will be distributed over the first 10 year inspection interval in accordance with Table IWB-2412-1..

5.4.2.4.2. 7 Examination Categories and Requirements The requirements for the first inservice inspection interval for San Onofre Units 2 and 3 steam gener ators is described both in the following paragraphs and in Section 4.0.5 of San Onofre's Technical Specification. Each component is discussed by categories corresponding to ASME Section XI, 1977 Edition through Summer 1978 Addenda.

5.4.2.4.2.7.1 Examination Category B-B, Pressure Retaining Welds in Vessels Other than Reactor Vessels A. Steam Generator - Items B2.30 thru B2.40 The outer steam generator head welds and the outer tube sheet welds will be volumetrically examined using manual techniques. The extent of weld examined will cover essentially 100%

of the weld length. The inner steam gener ator head welds (stay cylinder) and the inner tube sheet weld will be volumetrically examined using mechanized equipment. The extent of weld examined will cover essen tially 100% of the weld length.

5.4.2.4.2.7.2 Examination Category B-0, Full Penetration Welds of Nozzles in Vessels A. Steam Generator - Items B3.130 and B3.140 The steam generator nozzle-to-shell weld and nozzle inside radius section on the hot leg and two cold leg nozzles will be volumetrically examined from the outside manually.

At least one nozzle will be examined by the end of the first inspection period and the remaining two will be examined by the end of the first inspe.ction interval.

The extent of weld examined includes the nozzle-to-vessel weld and adjacent areas of the nozzle and steam generator for each of three nozzles.

5.4.2.4.2.6.3 Examination Category B-F, Pressure Retaining Dissimilar.Metal Welds A. Steam Generator - Item 5.30 There are no dissimilar metal welds on San Onofre, Units 2 and 3 steam generators.

5.4.2.4.2.7.4 Examination Category B-G-1, Pressure Retaining Bolting, Larger than 2 inches (51mm) in Diameter A. Steam Generator - Items B6.90 thru B6.100 There is no bolting on San Onofre, Units 2 and 3 steam generators which exceeds 2 inches in diameter.

5.4.2.4.2.7.5 Examination Category B-G-2, Pressure Retaining Bolting, 2 inches (51mm) and Smaller in Diameter A. Steam Generator - Item B7.30 Forty studs and forty nuts on the steam generator primary manway covers will be visually examined within the first in spection interval.

5.4.2,4.2.7.6 Examination Category B-H, Vessel Supports A. Steam Generator - Item B8.30 The steam generator is supported on a skirt integrally welded to the primary head of the steam generator. A surface examination will be performed on essentially 100% of the length of the weld and 1/2 inch on either side of the weld or one steam gen erator support.

5.4.2.4.2.7.7 Examination Category B-P, All Pressure Retaining Components A. Steam.Generator Items B15.30 and B15.31 During the system pressure test, which is conducted each refueling, a visual exam ination will be conducted for evidence of leakage to the rules of IWA-5000 and IWB-5000.

During the system hydrostatic test, which is normally conducted once each inspection interval, a visual examination will be con ducted for evidence of leakage to the rules of IWA-5000 and IWB-5000.

5.4.2.4.2.7.8 Examination Category B-Q, Steam Generator Tubing A. Steam Generator - Item B16.20 The steam generator tubes will be eddy current tested in accordance with this category and the recommendations of NRC Regulatory Guide 1.83 (Revision 1). San Onofre Units 2 and 3 steam generator

tubes, which are of the U-tube design, will have 3% of the installed heating surface eddy current tested. The exam ination area will include the entire hot leg, U-bend portion, and optionally the cold leg portion.

When San Onofre Units 2 and 3 technical specification requirements differ from those in Article IWB-2000, the Inservice Inspection Program for steam generator tubing will be governed by the require ments of the Technical Specification.

5.4.2.4.2.8 Evaluation of Examination Results In the conduct of San Onofre's inservice examination all indications which are required to be evaluated are done so to the acceptance standards of IWB-3000. If further evaluation is required the rules of ASME Section XI, Appendix A may also be utilized. Where the indication requires a repair on the component, these repairs will be conducted to the rules of IWA 4000 and IWB-4000.

5.4.2.4.2.9 System Leakage and Hydrostatic Pressure Tests As indicated in Section 5.4.2.4.2.7.7 all pressure re taining components receive a system leakage test each refueling and a system hydrostatic test once each in spection interval.

All pressure tests will be conducted to the pressure temperature requirements stated in the Technical Specification.

ENCLOSURE 4 SONGS 2/3 FSAR 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 6.6.1 Preservice Examination On October 18, 1973, San Onofre Units 2 and 3 were issued a construction permit for the two 1100 MWe pressurized water reactors. Relating this date to the requirements of 10CFR50.55a(g), the Preservice Examination (PSE) Program shall comply, as a minimum, to ASME Section XI, 1971 Edition through Summer 1972 Addenda. To minimize a change in scope between the preservice and inservice requirements, Southern California Edison upgraded the PSE Program to comply with the 1974 Edition through Summer 1975 Addenda.

Where these requirements were deemed impractical, a specific request for relief was written and docu mented in Appendix A of the Preservice Inspection Program plan. This plan was developed and submitted to the NRC for review in September, 1980.

6.6.2 Inservice Inspection San Onofre Units 2 and 3 Inservice Inspection (ISI)

Programs will comply, as a minimum, to the require ments of the latest edition and addenda of ASME Section XI which is incorporated by reference in paragraph (b) of 10CFR50.55a, twelve (12) months prior to the date of issuance of the license to operate at full power. Throughout the service life of San Onofre Units 2 and 3; components (including their supports) will meet these requirements, except for design and access provisions, to the extent .

practical within the limitations of design, geometry, and materials of construction of the component.

The ISI Program will be submitted for review six months before start of our initial 120 month in spection interval per.IWA-2400(b) so that compliance with 10CFR50.55a(g) can be demonstrated. Included in the ISI Program will be those exceptions taken during the preservice examination.

6.6.3 System Boundary Subject to Inspection San Onofre Units 2 and 3 ISI Program was developed to ASME Section XI, 1977 Edition through Summer 1978

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Addenda and the system boundaries for Class 2 and 3 pressure retaining components (and their supports) were developed to the requirements of USNRC Regula tory Guide 1.26.

The ISI Program includes those limitations and modi fications required of 10CFR50.55a(g) and identified in the October 9, 1979 Federal Register, Volume 44, No.

196.

6.6.4 Accessibility Access to examine ClassApressure retaining components, (and their supports) has been provided to accommodate either manual or mechantzed devices as warranted by the environment or location of the weld. Based on the preservice examtnation activities, this design provides adequate access to components, therefore, major ex ceptions to the rules of ASME Section XI are not re quired.

Provisions were incorporated into San Onofre Units 2 and 3 design to accommodate removal and storage of structural members, shielding components, and insulating material to permit access to Class 2 and 3 components being examined.

Hoists or other handling machinery needed to manipulate these structural members, shielding components, etc. were also provided.

6.6.5 Examination Techniques And Procedures San Onofre Units 2 and 3 ISI Program stipulates that the methods used for examination of Class 2 and 3 components are to be in accordance with ASME Section XI, Sub-article IWA-2200.

All visual examinations are conducted to the requirements of IWA-2210 and this technique is used to determine the general surface condition of a part or component.

All surface examinations are conducted to the requirements of IWA-2200 and these techniques are used on dry surfaces to detect the presence of surface or near surface cracks or discontinuities.

All volumetric examinations are conducted to the require ments of IWA-2230 and these techniques are used to detect the presence of subsurface indications.

If any alternative examination methods, combination of methods, or newly developed techniques are substi tuted for the above-described methods, results will be provided which demonstrate equivalence or superiority.

6.6.6 Inspection Interval The inservice inspection program was developed to the schedule of IWB-2412, Inspection Program B, and will be performed during normal plant outages such as refueling shutdowns or maintenance shutdowns during the inspection interval. All required examinations will be completed during each 10 year interval with the exception of those examinations that may be deferred until the end of the inspection interval, all required examinations will be distributed over the interval in accordance with Table IWB-2412-1.

6.6.7 Examination Categories And Requirements The requirements for the first inspection interval of San Onofre Units 2 and 3 Inservice Inspection Program is described both in the following paragraphs and in Section 4.0.5 of San Onofre's Technical Specification.

Each component is discussed by categories corresponding to ASME Section XI, 1977 Edition through Summer 1978 Addenda.

6.6.7.1 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels A. Pressure Vessels - Items C1.10 through C1.30 The pressure vessel circumferential head and shell welds and the tubesheet-to-shell weld will be ,

volumetrically examined from the outside, manually.

In the case of multiple vessels of similar size, design, and service, the required examination may be limited to one vessel.

The extent of weld examined for Item C1.10 through C1.30 will cover essentially 100% of the weld length.

6.6.7.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels A. Pressure Vessels - Items C2.10 and C2.20

The nozzles in vessels which are over inch in diameter will receive a surface and volumetric examination and the nozzles in vessels which are inch or less in diameter will receive a sur face examination by the end of the first inspec tion interval. These nozzles will only pertain to those piping runs selected for examination under Examination Category C-F.

6.6.7.3 Examination Category C-C, Support Members A. Pressure Vessels - Items C3.10 through C3.30 The steam generator support key welds at 00 and 1800 azimuth positions will receive a surface examination each inspection interval. This exam ination may beconducted on only one steam generator.

The regenerative heat exchanger supports will also receive a surface examination each inspection interval.

The extent of weld examined will cover 100% of the required areas for each support attachment.

The component supports, which include snubbers, will receive a visual examination each inspection interval.

Snubbers will also be confirmed for functional oper ability.

6.6.7.4 Examination Category C-D, Pressure Retaining Bolting Exceeding 2 inches (51 mm) in Diameter A. Pressure Vessels - Item C4.10 There is no bolting on San Onofre Units 2 and 3 pressure vessels which exceeds 2 inches in diameter.

B. Piping - Item C4.20 There is no bolting on San Onofre Units 2 and 3 piping which exceeds 2 inches in diameter.

C. Pumps - Item C4.30 There is no bolting on San Onofre Units 2 and 3 pumps which exceeds 2 inches in diameter.

D. Valves - Item C4.40 There is no bolting on San Onofre Units 2 and 3 valves which exceeds 2 inches in diameter.

6.6.7.5 Examination Category C-E, Support Members A. Piping - Items C3.40 through C3.60 Integral attachments welded to the pressure boundary will receive a surface examination on essentially 100% of the weld length. Those supports not associ ated with Examination Categories C-F and C-G or whose support base material'design thickness is 3/4 of an inch or less, will be excluded from examination.

The component supports, which includes snubbers, will receive a visual examination each inspection interval.

Snubbers will also be confirmed for functional opera bility.

B. Pumps - Items C3.70 through C3.90 Integral attachments welded to the pump pressure boundary will receive a surface examination on essen tially 100% of the weld length. Those supports not associated with Examination Categories C-F and C-G or whose support base material design thickness is 3/4 of an inch or less, will be excluded from examin ation.

The component supports, which include snubbers, will receive a visual examination each inspection interval.

Snubbers will also be confirmed for functional opera bility.

C. Valves - Items C3.100 through C3.120 There are no integral attachments or component supports on San Onofre Units 2 and 3 valves.

6.6.7.6 Examination Category C-F, Pressure Retaining Welds in Piping which Circulate Reactor Coolant Per the requirements of 10CFR50.55a(b)(2), the Code Class 2 pipe welds in the Residual Heat Removal Systems, Emergency Core Cooling Systems, and Contain ment Heat Removal Systems are being examined to the 1974 Edition through Summer 1975 Addenda.

A. Piping - Items C2.1 through C2.3 During each inspection interval all circumferential butt welds at structural discontinuities and in piping

within 3 pipe diameters of the centerline of rigid pipe anchors or anchors at the penetrations of the primary containment or at rigidly anchored components will receive a volumetric examination on essentially 100% of the weld.

In addition, all longitudinal weld joints in pipe fittings and all branch connection weld joints will receive a volumetric examination on essentially 100%

of the weld.

6.6.7.7 Examination Category C-G - Pressure Retaining Welds in Piping which circulate other than Reactor Coolant Per the requirements of 10CFR50.55a (b)(2), the Code Class 2 pipe welds in the Residual Heat Removal Systems, Emergency Core Cooling Systems, and Contain ment Heat Removal Systems are being examined to the 1974 Edition through Summer 1975 Addenda.

A. Piping - Items C2.1 through C2.3 During each inspection interval 50% of all circumfer ential butt welds at structural discontinuities and 50% of all circumferential butt welds in piping within 3 pipe diameters of the centerline of rigid pipe anchors or anchors at the penetrations of primary containment or at rigidly anchored components will receive a volumetric examination on essentially 100% of the weld.

In addition, 50% of all longitudinal weld joints in pipe fittings and 50% of all branch connection weld joints will receive a volumetric examination on essentially 100% of the weld.

6.6.7.8 Examination Category C-G, Pressure Retaining Welds in Pumps and Valves A. Pumps - Item 6.10 For those pumps which have welds in their casings, a surface examination will be performed each inspection interval on essentially 100% of the weld.

B. Valves - Item 6.20 For those valves which have welds in their casings, a

surface examination will be performed each inspection interval on essentially 100% of the weld.

6.6.7.9 Examination Category C-H, Pressure Retaining Components A. Pressure Vessels - Items C7.10 and C7.11 During the system functional test, which is conducted once each inspection period, a visual examination will be performed for evidence of leakage to the rules of IWA-5000 and IWC-5000.

During the system hydrostatic test, which is normally conducted once each inspection interval, a visual examination will be conducted for evidence of leakage to the rules of IWA-5000 and IWC-5000.

B. Piping - Items C7.20 and C7.21 Same examinations as specified in (A).

C. Pumps - Items C7.30 and C7.31 Same examinations as specified in (A).

D. Valves - Items C7.40 and C7.41 Same examinations as specified in (A).

6.6.7.10 Examination Category D-A, Systems in Support of Reactor Shutdown Function A. Class 3 Systems - Items D1.1 through D1.3 A visual examination for leakage will be performed under operating conditions of a system inservice test during each inspection period. Also during this same period, a visual examination will be performed on all component supports including snubbers, which exceed 4 inch nominal pipe size.

Once each inspection interval a visual examination for leakage will be performed on these Class 3 systems.

6.6.7.11 Examination Category D-B, Systems in Support of Emergency Core Cooling, Containment Heat Removal,,

Atmosphere Cleanup, and Reactor Residual Heat Removal A. Class 3 Systems - Items D2.1 through D2.3 A visual examination for leakage will be performed under the operating conditions of a system functional at least once each inspection period. Also during the same period a visual examination will be performed on all component supports, including snubbers, which exceed 4 inch nominal pipe size.

Once each inspection interval a visual examination for leakage will be performed on these Class 3 systems.

6.6.7.12 Examination Category D-C, Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool A. Class 3 Systems - Items D3.1 through D3.3 Same examinations as Examination Category D-A.

6.6.8 Evaluation of Examination Results In the conduct of San Onofre's inservice examination all indications which are required to be evaluated are done so to the acceptance standards of IWC-3000 and IWD-3000.

If further evaluation is required the rules of ASME Section XI, Appendix A may also be utilized. Where the indication requires a repair on the component, these repairs will be conducted to'the rules of IWA-4000, IWC-4000, and IWD-4000.

6.6.9 System Leakage And Hydrostatic Pressure Tests As indicated in Sections 6.6.7.9, 6.6.7.10, 6.6.7.11 and 6.6.7.12, all pressure retaining components receive a system functional test during operation and a system hydrostatic test once each inspection interval.

All pressure tests will be conducted to the pressure temperature requirements stated in the Technical Specification.

Class 2 components will be hydrostatic tested at a minimum pressure of 1.25 times the system pressure Psv for systems with Design Temperature above 2000 F and at a minimum pressure of 1.10 times Psv for systems with Design Temperature of 2000 F or less.

Class 3 components will be hydrostatically tested to the requirements of Class 2 components.

6.6.10 Augmented Inservice Inspection For those portions of high energy fluid system piping between containment isolation valves, a volumetric examination of essentially 100% of each circumferential and longitudinal pipe weld will be performed.

As discussed in paragraph 3.6A.2.4.3, main steam line jet impingement, line 1301-001 breaks 3 and 4 and line 1301-002 breaks 2a, 3 and 4 shall be inspected consistent with the NRC standard review plan 6.6 11.8 items (b) and (d).