ML072260452

Safety Evaluation Report, Supplement 1

ML072260452
Person / Time
Site:	Indian Point
Issue date:	11/20/1970
From:	US Atomic Energy Commission (AEC)
To:	US Atomic Energy Commission (AEC)
References
FOIA/PA-2009-0166
Download: ML072260452 (31)

Text

SUPPLEMENT NO. 1 TO AEC REGULATORY STAFF SAFETY EVALUATION IN THE MATTER OF CONSOLIDATED EDISON COMPANY INDIAN POINT NUCLEAR GENERATING PLANT UNIT 2 DOCKET NO. 50-247 November 20, 1970 Prepared by Division of Compliance U. S. Atomic Energy Commission I. INTRODUCTION This supplerhents the Safety Evaluation dated Novem-ber 16, 1970, prepared by the Division of Reactor Licensing of the Atomic Energy Commission (Commission or AEC) in con-nection with its review of the application of the Consoli-dated Edison Company (applicant) for an operating license for Unit 2 of the Indian Point Nuclear Generating Station located in the village of Buchanan,.in Westchester County, New York.The AEC regulatory program is founded in the Atomic Energy Act of 1954, as amended, and on implementing regula-tions and policies adopted by the Commission.

The Congress of the United States has established a system of licensing privately owned and operated nuclear facilities.

Inherent in the concept of private activities subject to licensing and regulation by aGovernment agency is the fact that the licensee is held responsible for meeting the objective of the licensing and regulatory system under the provisions of the Atomic Energy Act of 1954, as amended. The objective of the AEC program is to assure that licensed activities will not be inimical to the health and safety of the public or to the common defense and security.The Division of Compliance, as an-integral part of the Commission's regulatory staff, is responsible for conduct-ing the field inspections of AEC licensees to assure that--1-- licensed activities are in compliance with the provisions of AEC licenses; the Atomic Energy Act of 1954, as amended;and the rules and regulations of the Commission.

Division of Compliance inspections of nuclear power reactors under construction pursuant to an AEC construction permit pro-vide the principal basis for findings as to the status of completion of facility construction and the conformity of that construction to the requirements noted above.The Division of Compliance inspection program is con-ducted from five regional offices with each office having responsibility for the inspection of all AEC licensed ac-tivities within an assigned geographical area. The inspec-tion program at Indian Point Unit 2 is the responsibility of the Division of Compliance, Region I office located in Newark, New Jersey. A senior reactor inspector, who re-ports to the Regional Director, is responsible for super-vising the inspection program carried out by the various reactor inspectors.

Technical direction of the inspection program is provided by the Division of Compliance Head-quarters staff which gives direction to the region with respect to the conduct of inspection activities, gives technical support to the region when required, keeps the region informed concerning inspection experiences in other regions, evaluates adequacy of inspections and inspection results, and maintains liaison with other divisions of the AEC regulatory staff on matters which affect the in-spection program.The program for the inspection of the construction of Indian Point Unit 2 has been carried out primarily by Region I inspectors but, in addition, by Division of Com-pliance Headquarters staff, by other divisions of the AEC regulatory staff, and by consultants to the AEC. The principal activity of the inspectors has involved periodic inspections at the construction site. These site inspec-tions were conducted at non-regular intervals with the inspection frequency dependent on the activities which were in progress at the site. In addition to site inspec-tions, there were inspections at the shops of major equip-ment suppliers (vendors).

There were also inspections at the offices of the applicant and at its contractors for the purpose of inspecting construction records and procedures and engineering reports related to construction matters.Division of Compliance inspection personnel are ex-perienced and knowledgeable in the practical aspects of construction and operation of nuclear reactors.

In addition to the inspectors, specialists in appropriate fields of engineering and technology, who are assigned to the Di-vision of Compliance Headquarters staff and to other di-visions of the regulatory staff, are utilized to assist in special inspections.

Further, consultants to the AEC also provide assistance as required.

The experience and technical competence of inspection personnel are important factors in the effectiveness of the inspection program.The Division of Compliance inspection activities were directed toward verifying, on a planned sampling basis, that the licensee carries out his safety responsibilities and that the completed facility would conform to AEC regula-tory requirements.

Systems and components of the facility were selected for inspection on the basis of the regulatory staff's determination as to their importance to the safe op-eration of the facility.

These inspection activities in-cluded the following:

1. Review of the applicant's overall quality assur-ance and quality control programs and their implementation.

2. Inspection of quality control records.such as con-crete strength test data, material test reports for plate and piping, supplier certifications for piping, valves and fittings, and nondestructive test records for welding.3. Observation of construction work in progress;e.g., concrete placement, welding associated with vessel construction or piping installation, equipment alignment and installation, and non-destructive testing.4. Review of construction procedures; e.g., welding procedures and nondestructive testing procedures. 5. Witnessing the performance of major construction tests such as hydrostatic tests of piping and the pressure test of primary containment.

6. Review of program for functional testing of systems and equipment, including the tests planned, the test procedures, and the test results.7. Review of preparations for facility operations, including such areas as organization and staffing plans and their implementation, program and pro-cedures for fuel loading and power testing, de-velopment of routine operating procedures, maintenance procedures, radiation protection pro-cedures, and emergency procedures.

8. Review of component vendor work in progress, quality control activities and records, and fabrication procedures.

The licensee is required to develop and carry out a comprehensive preoperational testing program. The procedures developed under this program are reviewed by Compliance in-spectors and comments are directed to the licensee.

The performance of selected preoperational tests are witnessed by Compliance inspectors.

The results of the tests and the licensee's evaluations are reviewed by the inspectors.

This testing of the plant, to the extent possible prior to the loading of fuel, demonstrates whether plant systems and components are capable of performing their intended functions under both normal and abnormal conditions.

These tests also serve to demonstrate the adequacy of plant design and operating procedures.

Satisfactory completion of the pre-operational testing program is an important part of the basis for our findings of plant completion.

II. RESULTS OF CONSTRUCTION INSPECTIONS Since the issuance of Provisional Construction Permit No. CPPR-21 to the applicant authorizing construction of Indian Point Unit 2, inspections by the Division of Compli-ance have been conducted at the construction site, at vendor shops, and at the applicant's offices. A chronology of these inspections is attached as Appendix A. The results of the inspection of Unit 2, conducted through October 14, 1970, are discussed by systems in the same order as pre-sented in the Safety Evaluation dated November 16, 1970, prepared by the Division of Reactor Licensing.

A. Reactor Coolant System 1. Reactor Coolant Pressure Piping The reactor coolant pressure piping in-cludes the four primary recirculation loops, the pressurizer lines and portions of the fol-lowing systems: Chemical and Volume Control, Emergency Core Cooling (ECCS), Shutdown Cool-ing, Safety and Relief Valves, and Reactor Coolant Vent and Drain.

-7 Our inspection program was directed pri-marily toward auditing fabrication, erection, and nondestructive testing of the reactor coolant pressure boundary components and piping.The effort included site and vendor inspections utilizing our staff specialists.

The hydro-static test of the reactor coolant boundary at 125% of design pressure, which is required by the American Society of Mechanical Engineers (ASME) Code, has been conducted.

Portions of this test were reviewed and witnessed by Di-vision of Compliance inspectors and records of test results were examined to assure com-pliance with the code. In addition to the normal quality control inspections, a special quality control inspection was performed, under the direction of the assigned inspector, by a team of staff specialists, a specialist from the Division of Reactor Licensing, and a con-sultant. Segments of the reactor coolant system and emergency core cooling system (ECCS) were selected for inspection and review. Material certifications for selected portions of the re-actor coolant system components were examined. Onsite quality control records for the reactor coolant and: ECCS systems were examined and visual inspections of-these systems were performed.

Followup inspections hav.e been made to the site to complete the record review, and at the vendor shop which fabricated the ECCS piping.The applicant-and his contractor performed a review of quality control records for all pipe, valves, and fittings within the reactor coolant pressure boundary.

This review con-firmed the Division of Compliance findings that the reactor coolant system piping had not received the full hydrostatic test required by the applicable American Society for Testing Materials (ASTM) Code prior to leaving the manu-facturer's shop and that certain cast valve discs (7) had not been radiographed.

The sub-sequent performance of a field hydrostatic test of the system is considered to fulfill the code requirements.

• The necessity for radiographing the discs of the seven valves which do not perform a primary isolation function is being evaluated by the Division of Compliance and the Division of Reactor Licensing.

Completion Status: 'Construction of the pri-mary coolant piping is essentially complete.-.

Some installation of insulation and pipe hangers remains.2. Reactor Vessel The reactor pressure vessel was fabri-.cated at the shops of Combustion:Engineering, Inc., in Chattanooga, Tennessee.

The Division of Compliance performed in-spections at the shops during which fabrica-tion practices were observed, material quality records were examined, and nondestructive test-ing methods were reviewed.

We have followed.the placement of the vessel and fitup of the reactor core internals and installation of.the internals vibration detection instrumenta-tion. No deficiencies were identified.

Completion Status: Construction of the reactor pressure vessel and core internals has been satisfactorily completed.

3. Steam Generators Compliance performed a vendor inspection at the steam generator manufacturer's plant. This inspection included a review of quality control programs and related essentialý-docu-mentation.

The inspection disclosed records which indicated that insulation nut plate welds on the channel heads of the steam generators had not been magnetic particle tested. Sub-sequent magnetic particle testing of the welds was performed in the field. The Division of Compliance reviewed fitup and girth welding of the steam generators in the field. This activity included a review of welding pro-cedures, welder qualifications, and weld material certification.

Completion Status: Construction of the four steam generators has been satisfactorily completed.

4. Reactor Coolant Pumps The reactor coolant pumps have been in-stalled and have receivedan initial operation checkout.

We verified the pump materials and nondestructive testing performance for the re-actor coolant pumps during the special quality control inspection referred to in paragraph II. A. 1. of this report. Completion Status: Construction of the reactor coolant pumps has been satisfactorily completed.

5. Pressurizer The pressurizer has been installed.

We reviewed installation of the vessel and veri-fied that the code stamp indicated construction to applicable codes and regulatory requirements.

During pre-service ultrasonic testing of the pressurizer welds, nonmetallic inclusions in the base plate material were detected.The applicant conducted additional nondestruc-tive testing and technical reviews pertaining to the existing condition and concluded that a series of nonmetallic inclusions exist within the base plate material and that laminar de-fects beyond that allowed by the ASME Section III code do not exist. The applicant has submitted a report on this subject to the Division of Reactor Licensing.

The acceptability of these nonmetallic inclusions is under evaluation by the Division of Compliance and the Division of Reactor Licensing.

This issue will be resolved prior to licensing. Completion Status: Construction of the pres-surizer has been completed; however, satis-factory resolution of the above base plate material question will be required prior to licensing.

6. Pressure Relief and Safety Valves We have verified that the pressure relief and safety valves were installed and were set at the vendor shop to relieve at the designated pressure.Completion Status: Installation of these valves has been satisfactorily completed.

==

Conclusions:==

Based on the results of previous in-spections and corrective actions taken by the appli-cant and contractor to date, we conclude that there is reasonable assurance that the reactor coolant system will be completed in accordance with AEC regulatory requirements.

B. Containment and Class I Structures

1. Primary Containment The primary containment is a steel-lined reinforced concrete structure which houses the reactor coolant system. Our inspection program included selective examination of field fabrication procedures, observation of field fabrication activities, observation of non-destructive testing, and selective examination of onsite quality control. records.Problems identified by the applicant dur-ing construction of the primary containment included: a. A marked reduction in cadweld yield strengths was encountered.

b. The nominal diameter of the liner ex-ceeded tolerance limits in some instances.

c. Documentation on pipe penetration bellows materials and weldment quality is only partially traceable.

The applicant and his contractors investi-gated and resolved to our satisfaction problem a. and b. described above, and have initiated programs for correcting item c. Division of Compliance inspectors followed the progress of the completed investigations during inspections by the applicant at the site, and will follow those that are continuing for item c.Completion Status: The system will be con-sidered complete following concrete closure of one construction access opening, resolution of the penetration bellows question, completion of the integrated leak rate test, and instal-lation of the reactor coolant system leak detection equipment.

2. Other Class I Structures Other Class I (seismic) structures at Unit 2 include the primary auxiliary building, the control room, the fuel storage pool, diesel generator building, and the service water in-take structure.

Vacuum testing revealed leak-age at the welds of the fuel storage pool liner.The applicant and contractors have taken appro-priate corrective actions. We have inspected the construction of the other Class I struc-tures from the standpoint of construction practices and concrete quality. No problems were identified.

Completion Status: Construction of the other Class I structures is nearing completion.

Items to be completed prior to licensing are: a. Additional reinforcement of the Unit 1 superheater building (required be-cause of Unit 2 considerations) and the Unit 2 turbine building. b. Installation of a second completely independent turbine overspeed control.c. Provisions for alternate charging pump cooling water.d. Added missile protection for the auxiliary feedwater lines.Conclusions:

Based on our inspections to date, we conclude that there is reasonable assurance that the containment and other Class I structures will be completed in accordance with AEC regulatory requirements.

C. Engineered Safety Features 1. Emergency Core Cooling System (ECCS)The emergency core cooling system is com-prised of a high pressure system, a residual heat removal system, a recirculation system, boron injection tanks, and pressurized safety injection accumulators.

We have inspected the construction and examined quality control records for the ECCS during our normal inspections and the special quality control inspection.

Re-sults of our inspection included the following:

a. Welding quality control records incomplete. b. Visual inspection indicated a weak-ness in first line quality c~ontrol;i.e., weld splatter, arc strikes, and excessive grinding.c. Accumulator check valves which were not manufactured to Westinghouse specifications.

The applicant and contractor initiated corrective actions for these items and resolu-tion of each is nearing completion.

These items will be reviewed by the Division of Compliance to assure satisfactory resolution prior to licensing.

The applicant and his contractor performed a review of quality records for all pipe, valves, and fittings included in the reactor coolant pressure boundary, as described in paragraph II. A. 1. above. In addition, the applicant has reviewed quality control records for the remainder of the piping included in the ECCS system. The Division of Compliance has audited the results of this review and considers the findings to be acceptable.

Completion Status: Construction of the ECCS system is essentially complete.

Remaining work to be accomplished includes:

(1) finish surface cleanup, (2) completion of hanger and support installation, and (3) resolution of items listed above.2. Containment Spray and Fan Cooling Systems The containment spray system is comprised of two spray pumps and chemical additive de-vices. We have inspected the construction and examined quality control records for this system in conjunction with the ECCS.The containment fan cooling system is lo-cated within the containment.

The Division of.Compliance plans to complete inspection of this system during functional testing and filter testing prior to licensing.

Completion Status: Construction of the contain-ment spray and fan coolers is nearing completion.

Work remaining includes filter testing and functional testing.3. Post Accident Hydrogen Control System The post accident hydrogen control system has not been installed.

Installation of this system will be verified when completed. Completion Status: Installation of the hydro-gen control system will be completed prior to licensing of Unit 2.Conclusions:

Based on the results of our inspec-tions to date, we conclude that there is reasonable assurance that the construction of the Engineered Safety Features will be completed in accordance with AEC regulatory requirements.

D. Instrumentation, Control, and Power Systems These systems include the reactor protective, control, safety, and nuclear instrumentation and normal and emergency power. We have inspected the quality of the electrical and instrumentation installation, the separation and protection of key safety related circuits, and the loading of cable trays and wireways during the course of our normal inspection and, also, during the special quality control inspection.

Our inspection observations included the following:

1. Independent cable destgn review had not been performed.

2. Independent quality control of cable in-stallation was lacking. 3. Some redundant cables were not properly separated.

4. Items which required additional design analyses.The applicant and contractor initiated re-sponsive actions to correct the conditions noted above. Compliance has verified that their actions included a 100% design audit relative to the separation of power and control electrical cabling for redundant engineered safety feature and a design review on associated instrument cabling in excess of 95%. We have verified that work on the remaining items listed above is nearing com-pletion. These areas will require additional Compliance inspection effort to assure satisfactory completion prior to licensing.

Completion Status: Construction of the electrical and instrumentation systems is 95% complete.

Items remaining to be completed include: 1. Installation of remainder of separation barriers and fire stops.2. Completion of cable installation sur-veillance program.3. Installation of transite barriers at the single penetration area. 4. Installation of redundant power cables for the tunnel fans.Conclusions:

Based on the results of previous inspections and corrective actions taken by the applicant and contractor to date, we conclude that there is reasonable assurance that the instrumenta-tion, control, and power systems will be completed in accordance with AEC regulatory requirements.

E. Radioactive Waste. Control The radioactive waste control system includes facilities for processing and minimizing releases of liquid and gaseous effluents to the environment.

We have inspected the installation of the major components of these systems. The radiation mon-itoring instrumentation has not been installed and will be inspected for acceptable installation prior to licensing.

Completion Status: The radioactive waste control systems are essentially complete with the exception of the radiation monitoring instrumentation and controls.Conclusions:

Based on inspections to date and.the applicant's planned actions, we conclude that there is reasonable assurance that the radioactive waste disposal system will be completed in accordance with AEC regulatory requirements.

F. Auxiliary Systems Auxiliary systems includechemical.and volume control, residual heat removal, component cooling service water, and spent fuel storage.Completion Status: Construction is essentially complete.

Work to be accomplished includes instal-lation of some insulation, hangers and supports.Conclusions:

Based on the results of inspections to date, we conclude that there is reasonable as-surance that the auxiliary systems will be com-pleted in accordance with AEC regulatory requirements.

G. Conduct of Operation Conduct of operation as used here includes organization and staffing, preparation and review of procedures, and the administrative directives which the applicant has developed to conduct the functional testing program and subsequent operation of the Unit 2 facility.

We have verified that the applicant has established operational review and audit committees which are actively engaged in activities relating to plant startup. We have verified that the applicant has developed a program-21 for functional testing of equipment and systems and we have examined the available test procedures on a selective basis. We have also selectively examined the results of tests which have been completed.

We have initiated our review of the program and procedures for fuel loading, power ascension testing, and plant operation.

We plan to examine these procedures on a selective basis when their preparation has been completed.

Completion Status: Sixty percent of the preopera-tional test procedures have been approved for use by the applicant.

System functional testing is in the initial stages. Preoperational testing, including hot functional testing is scheduled to be completed prior to licensing.

==

Conclusions:==

Based on the results of our inspec-tion to date and responsive action taken by the applicant previously, we conclude that the ad-ministrative organization is in conformance with the application and that testing will be completed in accordance with AEC regulatory requirements.

III. CONCLUSIONS Based on the results of inspections of the Indian Point Unit 2 facility, we conclude that construction of the facility has been substantially completed in conformity with the construction permit and the application as amended, the provisions of the Act, and the rules and regulations of the Commission.

APPENDIX A CHRONOLOGY OF COMPLIANCE DIVISION INSPECTIONS CONSOLIDATED EDISON COMPANY INDIAN POINT NUCLEAR GENERATING STATION UNIT 2 Date Type Inspection Scope of Inspection 5/10-12/66 Shop Inspection

-Combustion Engineer-ing, Chattanooga, Tennessee I1/2/66 rrI 5/2/67 Site Inspection Management Meeting 5/24-26/67 8/1, 16, 22/67 Shop Inspection

-Combustion Engineer-ing, Chattanooga, Tennessee Site Inspection Inspected shop facilities and discussed procedures for fab-ricating the reactor vessel.Reviewed fabrication progress of reactor vessel. Observed work in progress and discussed fabrication techniques.

Initial meeting with Con Ed management to discuss Division of Compliance inspection program during reactor construction.

Reviewed fabrication progress, observed work in progress, and inspected records of welding, plate material properties and radiography.

Reviewed construction organization responsibilities.

Inspected con-tainment liner installation.

Reviewed quality control program for concrete, reinforcement bar and containment liner activities.

The program relating to blasting control was, discussed.

Reviewed corrective actions on containment liner bulge. Inspected records on containment liner plate and reinforcement bar materials.

Reviewed cadweld splice quality control program and information relating to decrease in cadweld strengths.

Inspected concrete compressive strength results.Reviewed blasting control program.11/29-30/67 Site Inspection Appendix A-2-Date Type Inspection Scope of Inspection 2/27-28/68 4/22-24/68 3/14/68 6/17-18/68 6/19/68 7/8-9/68 Site Inspection Vendor Inspection

-Combustion Engineer-ing, Chattanooga, Tennessee Site Inspection Site Inspection Site Inspection Vendor Inspection Chicago Bridge &Iron, Greenville, Pennsylvania Reviewed quality control records on cadweld splicing, concrete, contain-ment liner and blasting.

Reviewed quality assurance program relative to procurement of off-site components.

Reviewed records of reactor vessel fabrication.

Witnessed initial closure of reactor vessel head and hydrostatic testing of the vessel.Reviewed quality assurance programs and availability of records for procured components.

Inspected containment liner, cad-weld splice, concrete, and blasting records. Reviewed the spent fuel storage liner installation.

In-spected steam generator components and reviewed photographs of the steam generator movement from the barge to the site.Reviewed vendor inspection reports for procured components.

Reviewed purchase specification for the steam generators and the safety injection accumulators.

Reviewed purchasing, quality control, production, and records control for fabrication of the containment liner.Reviewed records pertaining to the containment liner, cadweld splicing and concrete.

Reviewed the material receipt inspection program and weld-ing procedures for the safety in-jection system. Inspected component storage areas. Visually observed the conditions relating to the steam generators and reactor vessel. An initial review of train-ing and preoperational testing was made.9/27 and 30/68 Site Inspection Appendix A-3-Date Type Inspection Site Inspection Scope of Inspection 10/8/68 11/20-21/68 1/7-9/69 1/20 and 24/69 Site Inspection Vendor Inspection

-Dravo Corporation, Marietta, Ohio Site Inspection Reviewed electrical design criteria relating to cable sizing and tray loading.Reviewed testing records for cad-weld splicing and concrete activities.

Reviewed actions taken to resolve quality deficiencies in the con-ventional and safety injection system pipe. Inspected the reactor vessel-, steam generators, and reactor coolant pumps for visible deficiencies.

Inspected fabrication and quality control records pertaining to pipe procured.Reviewed cadweld splicing and con-crete test records. Inspected records and procedures pertaining to field fabrication of the reactor coolant system and the steam gener-ator girth welding..

Reviewed resolution status of identified conventional pipe deficiencies.

Observed machining of the reactor vessel lower internal supports and electrical installation.

Reviewed records pertaining to cad-weld splicing and reactor coolant system welding. Inspected safety injection system weld records and field conditions.

Observed steam generator fitup and girth welding*and reviewed associated records.Inspected external storage of components.

Reviewed quality control programs and essential documentation for the steam generators.

3/4-5/69 It 3/18-21/69 Vendor Inspection

-Westinghouse Electric Corporation., Lester,.Pennsylvania Appendix A-4-Date Type Inspection Site Inspection.

Scope of Inspection 14/22-23/69 4/17 and 5/15, 22, 23/69 11 6/17, 7/1-2/69 Reviewed pipe specifications, vendor assembly records, storage and installation as related to investi-gations of piping fabricators' practices.

Reviewed quality control records for cadweld splicing, reactor coolant system welding, safety injection system site erection, and the spent fuel pit liner. Reviewed actions taken relative to safety injection and conventional system pipe component deficiencies.

Inspected revised steam generator girth weld procedures and records relating to this activity.

Reviewed activities associated with pipe fabrication investigations.

Inspected quality control records for cadweld splicing, concrete placement, and welding for the reactor coolant and safety injection systems. Reviewed electrical cable placement control programs and status of investigation relating to pipe procurement.

Inspected pipe supports, component outside storage and code stamping of components.

Reviewed progress relating to resolutions pertaining to pipe investigation.

Inspected portions of the safety injection system mechanical components to determine proper physical arrangements.

Reviewed welder and weld procedure qualification and welding performance for the control rod vessel head seal welds.7/23-24/69 Site Inspection Appendix A-5-Date Type Inspection Site Inspection Scope of Insoection 8/26, 27, 29/69 and 9/10/69 9/30/69 and 10/1-2/69 I?Reviewed the status of the pipe in-vestigation and the proposed organizational changes relating to the establishment of the Wedco, Inc.subsidiary of Westinghouse.

Observed reactor coolant system welding. In-spected the electrical cable place-ment and separations programs.Reviewed the physical layout and preoperational checkout of the fuel storage building.

Reviewed proce-dures for fuel element receipt and storage.Continued the review of the pipe investigation.

Reviewed welding records for the reactor coolant and safety injection systems. Inspected electrical cable placement progress and conformance to separation criteria.

Observed the initial receipt and handling of fuel assemblies.

Reviewed records relating to containment liner installation at the construction access openings.

Reviewed reactor vessel nozzle weld overlay procedures Observed attachment of reactor vessel internals vibration detectors and control programs for the vessel internals.

Team inspection to evaluate quality control of preselected portions of the reactor coolant, safety injection, main steam, and electrical systems.12/9-19/69 Quality Control Audit at the site, Con Ed Engineering offices, and Westinghouse Electric Company at Monroeville and Cheswick, Pennsylvania.

2/10/70 Management Meeting Discussed results of quality control audit performed in December 1969.

Appendix A-6-Date Type Inspection Site Inspection Scope of Inspection 1/22/70 and 2/6 and 11/70 3/26-27/70 4/10, 21, 22/70 5/6-8/70 5/22, 25, 26/70, 6/3, 11, 12, 15, 16/70 if Reviewed final status of pipe investigation.

Inspected the general preoperational test program and initial portions of system flushing and hydrostatic testing procedures.

Reviewed conformance to reactor pressure boundary criteria for installed components.

Continued inspection of preopera-tional testing program. Reviewed placement and surveillance activities for electrical cables, placement of cadwelds at the containment construc-tion access openings, and status of resolution of items identified during the Quality Control Audit.Continued inspection of the preopera-tional test program, electrical cable placement, and containment closure.Reviewed the proposed operating organization and status of operator training.

Reviewed installation of vibrational detection instrumentation for the core internals.

Continued inspection of preoperation test program, electrical installation and containment closure. Reviewed status of mechanical surface cleanup.Continued inspection of the preopera-tional testing program, electrical installation control programs, mechanical systems cleanup review, and evaluation of reactor pressure boundary components.

Made initial inspection of radiation monitoring and waste handling systems.it I I Appendix A-7-Date Type Inspection Site Inspection Scope of Inspection 6/26 and 29/70, 7/8-9/70 7/30/70 8/4, 5, 19, 244, 25/70 9/8, 23, 25/70 10/7, 8, 13, 14/70 if IT Witnessed the reactor coolant system hydrostatic test. Continued inspection of preoperational test programs, electrical installation reviews, and previously identified and unresolved items. Made initial inspection of the operating procedure program and nuclear facility safety committee structure and involvement.

Reviewed status of previously identified items requiring resolution.

Continued inspections of preopera-tional test programs.

Reviewed status of electrical installation, mechanical systems cleanup, reactor pressure boundary, and containment closure activities.

Reviewed conditions noted during preservice UT inspection of the pressurizer.

Continued inspection of preopera-tional test program, mechanical system cleanup & containment closure activities.

Reviewed installation control programs for pipe supports.Examined ultrasonic test data for the pressurizer base plate material.Continued inspection of the preopera-tional testing program, mechanical system cleanup, containment closure, and pipe support installation.

Reviewed pipe penetration bellows welding and materials documentation.

Continued inspection relating to reactor pressure boundary components, electrical design reviews, and electrical cable placement surveil-lance. Reviewed organization and involvement of the Nuclear Safety Committee.

Continued evaluation of the pressurizer base plate material.

Reviewed status of previously identified items requiring resolution.

I I