ML20211E458

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Rev 3 to Spec 9763.006-5-5, Spec for Structural Integrity Test (SIT) for Public Svc Co of New Hampshire,Seabrook Station,Unit 1
ML20211E458
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/12/1986
From: Bayer G, Bhatt K, Mudge T
UNITED ENGINEERS & CONSTRUCTORS, INC.
To:
Shared Package
ML20209E304 List:
References
FOIA-86-678 9763.006-5-5, NUDOCS 8610220453
Download: ML20211E458 (93)


Text

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E a constructors inc 30 South 17th Street Post Office Box 8223 Philadelphia, PA 19101 l

S12CIFICATION FOR STRUCTURAL INTEGRITY TEST (SIT)

FOR PUBLIC SERVICE COMPANY OF NEW RAMPSHIRE SEABROOK STATION UNIT NO. 1 Revisions No. Date Prep. Checked Q/A Approved By l By By SP ecification No.: 9763.006-5-5

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'K.M. Kalawadia Approved By: Ab J.J. Grams r The undersigned certifies that the information in this specification complies with the Subarticle CA-3360, i g,4 ?.' g,

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INDEX OF ECA/DCN CHANGES SPECIFICATION NO. 9763.006-5-5 DOCUMENT NO. AFFECTED SECTION REVISION - 3 ECA 01/807483B 8.5 t

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TABLE OF CONTENTS Page No.

GENERAL INFORMATION .I 1.0 SCOPE OF WORK 2 1.1 Purpose of Test 2 1.2 Unit 1 Information 2 1.3 Work Included 2 1.4 Related Work by Others 4 2.0 REFERENCE DOCUMENTS 6 2.1 Drawings 6 2.2 Codes, Standards and Specifications 6 3.0 GENERAL REQUIREMENTS 8 3.1 Responsibility 8 3.2 Personnel 8 i . .

4.0 '

INSTRUMENTATION 9 4.1 Displacements 9 4.2 DELETED 10 4.3 Concrete Crack Monitoring 11 4.4 Calibration 11 4.5 Instrument Reliability 12 4.6 Other Equipment, Supplies and Materials 12 5.0 PREDICTED INSTRUMENT RESPONSE 13 6.0 DELETED 14 7.0 PRETESTING 15 8.0 CONDUCTANCE OF THE SIT 16 9.0 POST-TEST WORK 18 10.0 TEST PLAN 19 11.0 TEST REPORT 20 f

  • Specification 9763.006-5-5 Page i

TABLE OF CONTENTS Page No.

12.0 QUALITY CONTROL 21 13.0 SUBMITTALS 22 14.0 - FOREIGN MATERIALS 23 FIGURE 1 Typical Section through Containment FIGURE 2 General Arrangement - Plan at El. 25'-0 FIGURE 3 Instrument Location '

FIGURE 4 Data Acquisition Area FIGURE 5 Proposed Increments of. Pressure FIGURE 6-9 Containment Stretch out concrete Maps for Structural Integrity Test APPENDIX A Proposed Format for Recording Data l

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Specification 9763.006-5-5 Page ii

GENERAL INFORMATION Owner Public Service Company of New Hampshire, et al.

1000 Elm Street Manchester, New Hampshire 03105' Engineering Supervisor Yankee Nuclear Services Division (TNSD) 1671 Worcester Road . .-

Framingham, Massachusetts 01701 Engineer - Constructor United Engineers & Constructors Inc.

30 South 17th Street

. P.O. Box 8223 Philadelphia, Pennsylvania 19101 construction Managers

, United Engineers & Constructors Inc.

30 South 17th Street P.O. Box 8223 Philadelphia, Pennsylvania 19101 Site Location Seabrook Station Approximately 6000 Feet East of Seabrook, NH at termination of Rocks Road Description The Seabrook Station is's two-unit nuclear plant. Each unit is rated at 1200 MWe and includes a four-loop PWR and a tandem compo' u nd, six-flow turbine-generator. The Structural Integrity Test (SIT) for Unit 1 is performed to demonstrate that the Containment responds in an acceptable manner to the specified internal test pressure of 115% of the design pressure.

The Integrated leak rate test (ILRT) will be conducted by others in conjunction with the SIT and will be performed af ter SIT peak pressure but prior to completing depressurization. It is expected that the ILRT will start at 39 psig SIT plateau and will take approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to complete.

Specification 9763.006-5-5 Page No. 1

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1.0 SCOPE 1.1 Purpose of Test The purpose of the SIT is to demonstrate the structural integ-rity of the Unit 1 Containment to withstand the postulated prea-sure loads in conformance with Appendix A of 10CFt50. In order to. demonstrate the structural integrity, the Containment will be subjected to increments of pressure up to the maximum test pressure of 60 pois (115% of the 52 peig design pressure). The ~

SIT shall be performed in accordance with USNRC Regulatory Guide 1.136 (Revision 2) and ASME Section III, Division 2, Article CC-6000 (1980 Edition).

Specific Articles of the ASME Section III, Division 2 are referenced in this Specification as CC-IIII.

Integrated Leak Rate Test (ILRT) is not within the scope of this specification.

1.2 Unit 1 Information

' The Consolidated Edison's Indian Point Unit No. 2'and Washington I public power supply system Unit No. I are the prototypes for this test. The PSNB Seabrook Station Unit 1 Containment is a non-prototype containment as defined in CC-6212.2.

l The Containment is shown on Figure 1 and General Arrangements i are shown on Figure 2 of this Specification. An enclosure building covers the containment and has a similar geometry.

i 1.3 Work Included The Contractor shall furnish all management, consultation,

' quality assurance, inspection and test personnel, supervision, labor, tools and equipment required to furnish, deliver, unload, install and monitor instrumentation and data acquisition system  ;

for the SIT. The work covered by this specification shall i include, but is not necessarily limited to, the followings 1.3.1 Prepara a Test Plan which will include all procedures.

1.3.2 Prepare instrument plan drawings, instrument support detail drawings and equipment layout drawings.

1.3.3 Prepare installation procedures, including calibration of all coc ractor supplied instruments and data acquisition checkout.

Specification 9763.006-5-5 Page No. 2 l

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1.3.4 Make recommendations for the surface preparations of all 1

concrete areas to be mapped.

i 1.3.5 Furnish and install all instrumentation and data acquisition equipment including connection to wiring, grounding and power cable (see Section 1.4.4).

1.3.6 DELETED 1.3.7 Design, furnish, fabricate, deliver and install all instrument

supports (see 1.4.17).

1.3.8 Furnish and install protection for SIT instruments which may be affected by test pressure and humidity in Containment causing damage to instruments or erratic behavior and malfunction.

1.3.9 Furnish consulting services with regard to instrument location, i

performance of test, including readiness to proceed to next pressure level, interpretation of test data during the test and j Final Report.

1.3.10 DELETED

, , 1.3.11 DELETED .

1.3.12 Furnish personnel to operate all instrument data acquisition equipment and computerized data conversion equipment during the pretest period, during the SIT and post test period.

1.3.13 Furnish personnel and instruments to map cracks before, during and after the SIT for specified areas (as shown on Figures 6 thru 9 and data recording Sheets A6 thru A9) and additional 3

areas as indentified by engineers from pretest inspection.

i 1.3.14 Furnish personnel to record all data (including deflection, temperature, pressure and time) during the SIT and post-test periods on data recording sheets s's required by the Engineers.

, 1.3.15 Provide photographs of instruments, data acquisition equipment j

' and all crack mapping areas (at each plateau of mapping) to augment the Test Plan and Test Report.

1.3.16 Maintain a daily' log of major activities during pretest, the SIT and post-test periods .

1.3.17 Furnish all expendable material, i.e., paper, writing and i marking supplies etc.

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Specification 9763.006-5-5 Page No. 3 i

i 1.3.18 Provide a quality assurance and control program and organiza-tion to meet the requirements of QAS-1, ANSI and the ASTM Codes.

1.3.19 Prepare a preliminary documentation package at completion of the. test and before leaving the site.

'1.3.20 Demobilize, including removal of all instrumentation, equipment and material.

1.3.21 Prepare a final test report as required by ASME III, Division 2.

1.3.22 Installation of all temporary support stands for displacement
instruments with limited assistance from UE&C construction.

1.4 Related Work by Others i

1.4.1 All accessibility for installation, calibration and removal of instrumentation and data acquisition equipment.

1.4.2 Platforms for mapping and monitoring concrete exterior cylinder and dome during the SIT.

1.4.3 Enclosed data acquisition area and maintenance of an exclusion area.

I 1.4.4 Furnish and install all wiring, grounding and power cables for Contractor's instrumentation and data acquisition equipment.

(In accordance with SIT Contractor's recommendations).

, 1.4.5 Inspection of interior of containment for equipment protection (other than Contractor's instruments) and structures which may affect or be affected by pressurization of the Containment.

1.4.6 Provide for temporary protection and/or removal of permanent equipment and structures inside Containment and their replace-ment after SIT.-

1.4.7 Provide temperature, pressure and time instrumentation in the Containment and furnish this data for recording.

1.4.8 Provide temperature instrumentation and control outside the Containment within the Enclosure Building and furnish data for recording.

1.4.9 DELETED 1.4.'10 Pretest and post test inspection of interior Containment Liner.

1.4.11 DELETED 1.4.12 Pretest and post test concrete containment structure inspection and identification of unusually severe cracks (see Section 1.3.13).

Specification 9763.006-5-5 Page No. 4

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1.4.13 Pressurization and depressurization of the Containment including all equipment and controls.

1.4.14 DELETED 1.4.15 DELETED 1.4.16 DELETED 1.4.17 Provide assistance for installation of all temporary support stands for displacement instruments (in accordance with the SIT Contractor's drawings and under his supervision).

1.4.18 Furnish SIT Test direction, composite test plan, test check-off list and procedure and data recording sheets.

1.4.19 Furnish predicted and acceptable deflections and crack mapping criteria.

1.4.20 DELETED 1.4.21 DELETED ,

t 1.4.22' Prepare Containment concrete surfaces of all areas to be mapped (in accordance with SIT Contractor's recommendations).

1.4.23 DELETED 1.4.24 Provide energized power source at 120 Vac outside the Containment (within the enclosure area) and in data acquisition area.

1.4.25 Provide all lighting, heating and ventilation in the Contain-ment before and af ter SIT and in the annulus area between the Containment and Enclosure Building at all times.

1.4.26 Trovide communication (radio and wire headset telephones) from monitoring stations to data acquisition area.

1.4.27 Provide all accessibility including fixed platforms, scaffolding, rigging and the use of the polar gantry crane and polar maintenance crane and the operation thereof.

1.4.28 Reproduction facilities and service for the copying of documentation at the site.

I 1.4.29 Evaluation of structural behavior of Containment during and

] after the test.

I 1.4.30 Final Report (which will include SIT Contractor's . Test Report).

Specification 9763.006-5-5 Page No. 5

l 2.0 REFERENCE DOCUMENTS 2.1 Drawings The attached " List of Drawings" includes reference drawings.

Reference Drawings serve to supplement all information obtained from the Contractor's site visits as required in the performance of his work.

2.2 Codes, Standards and Specifications The following codes, standards and specifications shall be considered an integral part of this specification.

2.2.1 American Society of Mechanical Engineers (ASME)

ASME Boiler and Pressure Vessel Code,Section III, Division 2, 1980 Edition,' Article CC-6000.

2.2.2 United States Nuclear Regulatory Commission (USNRC)

USNRC Regulatory Guide 1.136, Rev. 2 (1981).

t 2.2.3 American National Standards Institute (ANSI)

  • ANSI - N45.2 Quality Assurance Requirements for Nuclear Power Plants.

ANSI - N45.2.2 Packaging, Shipping, Receiving, Storsge and Handling of Items for Nuclear Power. Plants.

ANSI - N45.2.6 Qualifications of Inspection, Examination and Testing Personnel for Construction of Nuclear Power Plants.

ANSI - C1 The National Electric Code (1978).

2.2.4 Code of Federal Regulations (CFR) 10CFR50 Appendix A-Ceneral Design Criteria for Nuclear Power Plants - General Design Criteria 1, Quality Standards and Records - 1971.

10CFR50 Appendix B-Quality Assurance Program Requirements for Nuclear Power Plants and Reprocessing Plants - 1971 f .

Specification 9763.006-5-5 Page No. 6

2.2.5 U.S. Dept. of Labor, occupational Safety and Health Administration (OSHA)

OSHA Public Law 91-596 (Code of Federal Regulations 29CFR 1910, 19CFR 1926), (1970).

2.2.6 United Razineers & Constructors Inc.

9763-QAS-1 Quality Assurance Administrative and System Requirements for Nuclear Safety Class Items 9763-NPS-1 Material and Processing Requirements TP-13* Technical Procedure for General Requirements for SIT 9763-RN-1 Instructions for Site Management System i

  • Included for information only.

Specification 9763.006-5-5 '

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3.0 CENERAL REQUIREMENTS 3.1 Res ponsibility The Contractor is responsible to make recommendations for all instruments and data recording equipment, furnish and install all instruments and data recording equipment as approved by the Test Director and the Engineer, operate all equipment, report the results and observations (in the format acceptable to the Engineer) and provide any explanation / identification of any divergence of actusi results from those predicted results furnished by the Engineer related to instrument behavior.

The engineer and the test director reserve the rights to relocate crack mapping areas and displacement measurement areas to suit field conditions.

The Contractor shall prepare the Test Report which will be a part of the Final Report prepared by the Engineer.

3.2 Personnel The Contractor shall provide experienced, trained test

[ personnel, supervision and senior test engineers at the site during pretest, the SIT and the post-test periods.

A Quality Assurance Manager shall be provided in accordance with ASME III Division 2'and ANSI N45.2 requirements.

All personnel performing inspection, examination, testing and reporting shall be qualified and certified in accordance with ANSI N45.2.6 requirements.

3.2.1 DELETED 3.2.2 DELETED i

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t Specification 9763.006-5-5 Page No. 8 l

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4.0 INSTRUMENTATION 4.1 Displacements 4.1.1 The Contractor shall furnish and install invar wire, positive displacement instruments and instrument supports to measure displacements / deflections of the concrete cylinder, done and other locations as shown on the Instrument Location Flan (see figure 3).

4.1.2 Invar wire shall be cold drawn, round wire free of kinks and installed such that true displacement / deflection can be monitored and measured. The Contractor shall submit a material specification of the wire including size, and physical properties including coefficient of expansion, tensile strength ~and modulus of elasticity for information to the Engineer. A procedure for installation of wires including tension and sag shall also be submitted.

4.1.3 Transducers shall be capable of recording at a minimum of 18 pounds invar wire tension and set to record displacements in accordance with CC-6232.1. The range of instruments shall be determined by the Contractor based on his experience and Code

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4.1.4 Data acquisition equipment shall record or convert displacement / deflections directly to inches.

4.1.5 Dome deflection data measured from diagonals shall be utilized to compute the true vertical deflections of the done in inches.

4.1.6 Vertical deflections of the top of Containment cylinder relative to the base of the Containment are to be' measured from fixed points near the operating floor structure (EL. 25'-02)on four azimuths. The operating floor structure is isolated from containment cylinder wall and not affected by the internal pressure. Therefore, the vertical deflection of the top of the cylinder is measured relative to the base of the Containnent in accordance with CC-6232(c).

4.1.7 In addition to 4.1.5, the vertical deflection of the apex of the done is measured by two independent diagonal wires attached to the top of steam generator shield wall at EL. 33'-0.

i i Specification 9763.006-5-5 Page No. 9 l

1 4.1.8 Deflections measured horizontally across the Containment diameter may be measured at one point and the recorded deflec-tion averaged to determine the radial deflection at each

opposite end of the wire in accordance with CC-6232.
4.1.9 Instrument locations for the Containment cylinder and done may l ' be relocated within one foot of the location shown on the drawing without the Engineer's approval. Instrument locations for the radial measurements at the equipment hatch and personnel air lock may be relocated within six . inches of the location shown on the drawing without the Engineer's approval.

All other changes in instrument locations shall have the Engineer's approval.

4.1.10 Instrument supports should not be Welded to permanent structures and should not be placed on Welded joints unless otherwise approved by the engineer. Magnetic and any other means of attachment which could adversely affect the reading should not be used. Procedure for attachment should be submitted for approval by the engineer.

4.1.11 The Contractor's test report shall show the precise "as-built" location of these instruments.

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  • 4.1.12 Instrument support stands wherever required shall be designed, fabricated and delivered for installation by others. The Contractor shall furnish installation drawings and field su pervision. Where anchors are required in interior concrete walls or floors, provrsion shall be made to allow for location adjustment to clear reinforcing steel.

4.1.13 All displacements / deflections shall be measured and recorded at j each pressurization and depressurization plateau.

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4.2.1 DELETED 4.2.2 DELETED 4.2.3 DELETED I

i Specification 9763.006-5-5 Page No. 10

4.3 Concrete Crack Monitoring 4.3.1 The Contractor shall use a 6X measuring microcomparators or better to measure concrete cracks. The Contractor shall furnish (10) additional microcomparators for the use of others (on a rental basis) during pretest inspection. These will be -

sent to the Construction Managers in advance for use in training personnel.

4.3.2 The Contractor shall recommend to the Construction Managers the i

preparation of concrete surfaces to be mapped. A grid system shall be marked on the concrete surfaces to be used in recording on maps at the observation areas and to communicate concrete crack widths and locations to the data acquisition area where similar maps wi_11 be marked up by this Contractor.

See Appendix A, Sheets A6 thru A9.f.

4.3.3 All concrete cracks 0.01 inches in width or greater shall be mapped and monitored at the preselected areas by this Contractor.

Concrete cracks shall be measured and recorded in increments of

.001 inches in width and 1.0 inches in length.

4.3.4 The Contractor shall also monitor and map all concrete cracks f designated by the engineers as determined from the engineer's pretest inspection. Incremental changes shall be measured and

  • recorded as specified in Section 4.3.3.

4.3.5 Platforms and/or scaffolds will be provided by others to facilitate monitoring and mapping.

4.3.6 Cracks shall be monitored and mapped at each pressurization plateau and at 39 psig and 0.0 peig'depressurization plateaus.

j 4.4 Calibration

, 4.4.1 Instrumentation shall be calibrated before it is delivered and installed or used, after installation during the pretest period and just before removal after the SIT is completed and 24-hour recovery period has elapsed.

4.4.2 All instrumentation calibration shall be against certified measurement standards which have known valid relationships to National Standards. Should no National Standard exist, the Contractor shall document the basis of his calibration to the

satisfaction of the Construction Managers.

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Specification 9763.006-5-5 Page No. 11

4.4.3 A calibration procedure shall be prepared for approval by the l Construction Managers, Engineers and the Test Director and the  !

approved procedure included in the Test Plan.

4.4.4 DELETED 4.5 Instrument Reliability 4.5.1 All instrumentation and equipment required to meet this specifi-cation shall be demonstrated to perform their function at the site or at the contractor's location as approved by the test director and the engineer.

4.6 Other Equipment, supplies and Material 4.6.1 The Contractor shall furnish all materials, dispensible sfupplies, tools and special equipment required to install instrumentation and data acquisition equipment required to facilitate the recording of data as required for the SIT.

4.6.2 Restriction of materials for use in Containment is specified in Section 13.0 in accordance with UE&C Specification 9763-MPS-1.

Where such materials are unavoidably required, the Contractor

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shall submit a written request to the Construction Managers for relief.

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3 Specification 9763.006-5-5 Page No. 12

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1 5.0 PREDICTED RESPONSE AT PEAK PRESSURE I 5.1 DISPI.ACEMENTS The predicted displacements at peak pressure are approximately as follows:

Cylinder maximum radial displacement 1.05 inches Cylinder vertical displacement -

at the springline relative to the base 1.33 inches Vertical displacement of the dome at the apex 2.20 inches Equipment hatch inside diameter growths

Horizontal 0.35 inches Vertical 0.10 inches Equipment hatch maximum radial displacement 1.0 inches i .

Personnel air lock inside -

diameter growths:

Horizontal- 0.10 inches Vertical 0.04 inches Personnel air lock maximum radial displacement 1.0 inches 5.2 CRACK WIDTHS The prediction of crack pattern and widths is based on behavior of prototype containments. The predicted maximum crack widths at peak pressure in the membrane regions (excluding disecnti-nuity regions around large openings) are expected to be 0.025 inch or less, spaced approximately 18 inches. Crack widths in the vicinity of large openings, such as equipment hatch and personnel airlocks may be, greater. The acceptance criteria for cracks are as follows:

a. The maximum crack width at peak pressure of 60 psig is 0.035 inch averaged over a length of 20'-0; the minimum spacing is 15". These averages exclude crack patterns in the vicinity of large openings.
b. Crack widths after depressurization are predicted to be less

, than 0.01 inch. .

Specification 9763.006-5-5 Page No. 13

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6.0 DEUTED i .

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1 i SP ecification 9763.006-5-5 Page No. 14

7.0 PRETESTING 7.1 DELETED 7.2 Contractor shall operate data acquisition and checkout his instrumentation, perform calibrations and make adjustments as necessary. Instruments exhibiting erratic or other improbable behavior shall be repaired or replaced.

7.3 The Contractor shall maintain a los to record all pretest data and activities.

7.4 Temperature and pressure data shall be monitored by others and the information given to the Contractor for entry in the log.

7.5 Log shall consist of looseleaf reproducible pages; all entries shall be legible. Contractor's Senior Test Engineer, the Contractor's QA/QC personnel and the Test Director shall sign on the log. The Test Director reserves the right to edit the log and make entries as he deems appropriate. Copies of the log will be made and distributed to authorized personnel.

7.6 Contractor shall provide a written acceptance of material and

, installation of wiring, grounding and power cable provided by others. -

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Specification 9763.006-5-5 Page No. 15

8.0 CONDUCTANCE OF THE SIT 8.1 The SIT will be under the direction of the Test Director, in accordance with the Test Plan (See Section 10) and in compliance with the Code. The Test Director will be an individual from the NRY Startup Test Department. ,

8.2 Figure 5 shows the planned pressurization and depressurization schedule and pressure plateaus.

8.3 ' All instrumentation recording will be conducted one hour after each pressurisation and depressurization plateau has been reached at the direction of the Test Director.

Final displacement / deflection will be measured and recorded just prior to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> recovery period elapses at the direction of the test director.

8.4 Af ter recording on Data Recording Sheets (see Appendix A) and mapping of concrete cracks are complete, the results will be evaluated by the Test Director, the Engineer and the Contractor's Senior Test Engineer. The checkoff list will be signed off authorizing pressurization or depressurization to the next plateau.

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  • 8.5 The checkoff list will be signed off by the Contractor's Senior Test Engineer, the Engineer and finally by the Test Director.

The Test Director is responsible to initiate the directive to continue to the next recording plateau.

8.6 Checkoff lists for each recording plateau will be prepared by' others.

8.7 The Containment will be pressurized and depressurized by others under the direction of the Test Director. Atmospheric (oil-free) air will be used as the testing fluid. Pressurization shall be at a uniform rate at approximately 2. psig per hour but not to exceed 3.5 psig Per hour. Depressurization shall be at a uniform rate of approximately 4 psig par hour but not to exceed 5.0 pais/hr. Pressurization tolerances are given in Figure 5.0. Humidity in the Containment will be monitored by others. Temperature outside the containment, within the enclosure building will be monitored and controlled so as to maintain a minimum temperature of 300F and also the average differential temperature between the inside of containment and outside of containment within enclosure building does not exceed t .

Specification 9763.006-5-5 Page No.16 i

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650F. All dates, time, pressure and temperature data vill be given to the SIT contractor for recording. Pressure will be held at each plateau until all data (with the exception of photographs of crack mapping area) is recorded and evaluated and checkoff list signed off.

8.8' DELETED n

l Specification 9763.006-5-5 Page No. 17

9.0 POST-TEST WORK 9'.1 Instrumentation Check Immediately following the 24-hour stabilization period, the Contractor shall check all instrumentation, recalibrate instru-ments noting differences and adjustments required and evaluate the performance or malfunction. The Contractor's Senior Test Engineer shall complete the Instrument Recovery Data Form (Appendix A).

9.2 All activity shall be recorded in the log.

9.3 After the completion of the test, and all data has been recorded, concrete cracks mapped and instruments checked for recalibration, the Contractor shall prepare a Certificate of Conformance for field work attesting to the completion of all work in accordance with the Codes and this specification. The Certificate will be executed by the Contractor's Senior Test Engineer and QA personnel.

9.4 Before leaving the site, the Contractor shall prepare a i

reproducible documentation package consisting of the followl,ng:

9.4.1 Completed Log 9.4.2 Printouts of data acquisition equipment identified to date, time and pressure.

9.4.3 Completed data recording sheets.

9.4.4 Maps of concrete crack monitoring.

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Specification 9763.006-5-5 Page No. 18 i

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10.0 TEST P1.Att 10.1 The CAhtractor shall submit a portion of the Test Plan as noted i

below to tho' Test Director and the Engineers for approval. The final test plan, when complete, will be issued to the Contractor for review and comments.

10.2 The portion of the Test Plan furnished by the SIT Contractor shall include the--following as a minimum.

10.2.1 Description of instrumentation, including type, manufacture, range, tolerance and the function of each instrument.

10.2.2 Installation procedures including ca'11bration.

! 10.2.3 Description of'all data acquisition and retrieval systems' along with'agnipment utilised for checkout. Equipment source including manufacturer and function with respect to data

required to complete the SIT recording sheets.

10.2.4 Description of all conversion equipment together with samples illustrating method of conversion, i.e., vertical deflections from diagonal invier ~ wire deflection data.

4 l'O.2.5 Correction criteria to be applied (if required) to raw data to '

account for wire sag, temperature change, displacement reversals, etc.

10.2.6 DELETED j

10.2.7 Function of test personnel to be provided during pretest, the SIT and post-test periods. This shall include operators for equipment and inspection and mapping personnel. The respon-

! sibilities of the Senior Test Engineers and QA personnel shall

also be defined.

t l 10.2.8 An instrument plan drawing and layout of equipment in data acquisition area. The location of the data acquisition area is shown on Figure 4.

10.2.9 DELETED 10.2.10 The Contractor's portion of the Test Plan shall be a photo-ready reproducible document issued well in advance of the SIT (See Section 13.0). The preliminary test plan as submitted l to the Test Director and the Engineer shall be subject to their i

review and approval. All changes to the Centractor's part of j the Test Plan shall be done by this Contractor as requested.

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l 11.0 TEST REPORT 11.1 The Contractor shall submit to the Engineer and the Test Director a Test Report which shall be made a part of the Pinal Report prepared by the Ecgineer. ,

11.2 The Test Report prepared by the Contractor shall include the following as a minimmt a) A description of the test procedure. This shall include an edited portion of the test plan and the procedures required by this Contractor together with the discription and final location of all instrumentation.

b) A completed formal data acquisition form.

c) A summary of the results of all test measurements made by this contractor and others and an evaluation of the accuracy of the seasurements.

d) A discussion and sample computations of all corrections made to raw data due to wire sag, temperature, response

, lag, etc. -

e) An evaluation and discussion of instrumentation malfunc-tions, and possible causes, measurements which should i be neglected due to inaccuracy with proper justification, malfunction or drift and the disposition of the deviations during the SIT.

f) Signature and seal of Registered Professional Engineer certifying to conformance with CC-6000.

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Specification 9763.006-5-5 Page No. 20

12.0 QUALITY CONTROL 12.1 The Contractor's Quality Assurance and Inspection program shall meet the requirements of Specificatica 9763-QAS-1 and as specified herein.

12.2 The Contractor shall establish and maintain documented Quality

  • Assurance procedures for instrument installation and testing activities which shall conform to this Specification and applicable Sections of ANSI N45.2 and-ASNI III, Division 2. -

12.3 QA Records l

12.3.1 After completion of.the work, the Contractor shall turn over to the Test Director a complete documentation package of QA records. The QA documentation package shall include but is not limited to the followings a) Personnel Certifications (including Level 7.II Inspector).

b) List of all measuring and test equipment used and their associated calibration records

( c) Nonconfomance Reports, inspection and test records.

d) A copy of the Executed Certificate of Conformance of field work.

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Specification 9763.006-5-5 Page No. 21

13.0 SU5MITTALS 13.1 The Contractor shall submit the following Procedures and docu-ments to the Engineer and Test Director for approvals a) Test Plan (as applicable) b) Instrument Plan Drawing

  • and squipment Layout Drawings c) Procedure for installation of Instrument supports, Instruments and their Calibration before and after SIT and for conduct of test
  • d) Instrument support detail drawings e) QA Manual as amended for this Project
  • f) Procedure for mapping and

( recording ,

Concrete Cracks

3) Document Packages *

(QA & Test) h) Test Report

1) Personnel Qualification Procedures
  • j) Procedure for inspection of all work performed *
  • Documents which also require UE&C QA approval.

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Specification 9763.006-5-5 Page No. 22

14.0 FOREIGN MATERIALS In conjunction with UElec Specification 9763-MPS-1, care sha'11 be taken to prevent contamination by foreign materials in the Containment. Temporary plugs or seals shall be installed to keep contaminants out of a clean component during subsequent fabrication, shipping, storage and erection. Precautions shall be taken to prevent such temporary plugs and seals from being inadvertently left in the component when installed.

14.1 Lead or other Low-Meltina Metals Compounds or materials containing low melting metals as a basic chemical constituent shall not be used in direct contact with the surface of equipment or components at any time. This prohibition includes tooling, fixtures, marking materials, fluxes, temperature crayons, paints, coatings, etc., used during installation operations.

14.2 Mercury During the manufacturing processes, tests and inspections, the component or system shall not have come in direct contact with mercury or any of its compounds nor with any mercury containing devices employing a single boundary of containment. Manome-ters, vacuum pumps, or other instrumentation or equipment containing mercury or mercury compounds shall not be used.

14.3 Iron Free Iron contamination shall not be present on the surfaces of austenitic base materials when the component or material is to be subjected to temperatures above cubients e.g. heat treating, stress relieving, welding, etc.

l 14.4 Sulfur Sulfur and sulfur compounds or materials containing sulfur as a basic chemical constituent shall not be used in direct contact with the surface of nickel base alloys, nor shall sacerials containing more than 250 PPM of sulfur in leachable form or potentially leachable fom be used.

14.5 Aluminum Aluminum shall not be used either as soft pads or hammers to reduce marring during assembly and handling of nickel base or stainless steel alloy components. Aluminum pipe caps and seals shall not be used on stainless or nickel base alloy components.

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Specification 9763.006-5-5 Page No. 23

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l 14.6 Zinc, Cadmium and Copper Zinc, Cadmiuu and copper, and their alloys shall not be allowed to come in contact with stainless steel surfaces, 14.7 Paint The painting of corrosion-resistant material is prohibited. If paint has been inadvertently applied-to corrosion-resistant materials, it shall be removed using new or redistilled methyl ethylketone (CH3 C0C2 55) followed by rinsing with acetone or alcohol. If this method fails, the paint shall be removed using simple mechanical cleaning methods with austenitic stainless steel tools such as wire brushes, steel vool or scraping devices.

Following this mechanica1' cleaning, the part should be washed with either domineralized or filtered water as applicable.

14.8 Tapes

.The use of tape in conjunction with temporary plugs, seals, identification or for any other reason shall meet maximum leachable chloride and fluoride limits of 15 PPM and 10 PPM, g gespectively. When used, both the tape and tape residue ,

(athesive) must be completely ' removed from materials surfaces, prior to system use and to any heat treatment of fabrication operations which rendor the tape inaccessible. Removal shall be accomplished by new or redistilled alcohol or acetone.

Abrasive cleaning methods may be necessary to supplement and improve the solvent action.

14.9 Contamination controls 14.9.1 All austenitic (e.g., type 300 stainless, Ni-Cr-Fe alloys) materials of construction shall be free from low melting point materials such as alloying censtituents e.g., lead, sinc, cadmium, tin, antimony, mercury, bismuth, phosphorous and misch metal and'their compounds. Lead or other low melting constituents or their compounds or materials containing low melting metals as a basic constituent shall not be used in direct contact with the surface of equipment or components at anytime. This prohibition ,

includes loading fixtures, marking materials, fluxes, temperature indicating crayons, paints, coatings, etc. used during fabrication, installation and operation.

14.9.2 Stainless steel shall not come in contact with halogen containing compounds such as fluorides and chlorides, except for Engineer approved liquid penetrant solutions, which must be removed immediately after the test.

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Specification 9763.006-5-5 Page No. 24

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i 14.9.3 surlfur, sulfur compounds or materials containing sulfur'as a basia chemical constituent shall not be used in direct contact with the surface of nickel base alloys.

14.9.4 Aluminum shall not be used as sof t pads or hammers to reduce surface damage during assembly and handling of nickel base or stainless steel components. Aluminum pipe caps and seals shall not be used on stainless or nickel base alloy components.

14.9.5 The manufacturing process, tests, and inspections, shall not cause the component or system to come in direct contact with -

mercury or any of its compound nor with any mercury-containing devices employing a single boundary of containment.

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1 Specification 9763.006-5-5 Page No. 25

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6 O APPENDIX A ' TO SPECIFICATION 9763-006-5-5 DATA RECORDING t. e

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i l l l LIST OF DRAWINCS to Accompany Specification 9763.006-5-5 1 1.0 Reference Drawings i The following drawings are for information: Drawing No. Title 9763-F-101440 Concrete - Equipment Hatch Reinforcing 9763-F-102153 Enclosure Building Platform UE&C FSK 329 Containment Interior, Unit 1, Temporary 2-Ton Trolley Monorail FP 48315 Structural concrete Containment Dome FP 48316 Structural Concrete Containment Dome 9763-F-102315 containment Steel Framing Plans at E1.0'-0 and 25'-0" (West) 9763-F-102317 Containment Steel Framing Plans at E1.0'-O' and 25'-0" (South) 9763-F-102319 Containment Steel Framing Plans at E1.0'-0 and 25'-0" (North) 9763-F-102321 Containment Steel Framing Plans at E1.0'-0 and 25'-0" (East) 9763-F-101940 Containment Steel Framing Plans at E1.12'-9" (East) 9763-F-101941 Containment Steel Framing Plans at E1.12'-9" (West) 9763-F-101406 Containment Concrete Plan at E1.0'-0" 9763-F-101407 Containment Concrete Plan at E1. 25'-0" 9763-F-101487 Containment Concrete Plan at El. O'-0" (Annulus Area) Sheet 1 of 2 l

i l Drawing No. Title 9763-F-101488 Containment concrete Plan at El. 25'-0" (Annulus Area) 9763-F-101434 Containment concrete Sections and Elevations 9763-F-101420 Containment Concrete Interior Sections sheet 7 9763-F-101461 Containment Liner Details and Attachments 9763-F-101495 Containment Liner Vertical Wall 9763-F-101496 Containment Liner Wall Openings and Penetrations s I j Sheet 2 of 2

1 1 e J T CONTAINMENT STRUCTURAL INTEGRITY TEST SEABROOK STATION - UNIT 1 APPENDIX D g SIT PREDICTED AND ACCEPTABLE DATA

   !                                                  SB-1 SIT Page No. D-1 4

i l I k APPENDIX D SIT PREDICTED AND ACCEPTABLE DATA 1.0 PURPOSE To prove the adequacy of the Containment with respect to quality of construction and material, the Containment was pressurized to 60.0 psig (1.15 times the . design accident pressure of 52 psig) internal pressure load. Various measurements of the Containment were taken at each stipulated pressurization and depressurization plateu as indicated below:

a. Displacement measurements were taken at pressurization plateaus of 0, 13, 26, 39, 52, 60 psig and depressurization plateaus of 52, 39, 26, 13, 0 psig. .See Figure 5 in Appendix C.
b. Cracks were monitored and mapped _at each pressurization plateau and at 39 psig and 0.0 psig depressurization plateaus. See Section 4.3 in Appendix C.

This Appendix provides various predicted and acceptable data to determine whether the Containment is responding satisfactorily to f internal pressures as predicted analytically. The criteria given in this Appendix were used to decide whether it was safe to pro-ceed with the pressurization of the Containment to the next higher pressure plateau. Tables D-1 through D-7 provide predicted analytical and acceptable levels of displacements of the Containment for various pressure plateaus. 2.0 INSTRUMENTATION AND TEST REQUIREMENTS 2.1 General Instrumentation and test requirements are in accordance with the following documents:

1. USNRC Regulatory Guide 1.136, Rev. 2, June 1981 (Appendix A).
2. Article CC-6000 of ASME B6PV Code, Section LII, Division 2, 1980 Edition (Appendix B).
3. UE&C Specification for Structural Integrity Test, Specifica-tion No. 9763.006-5-5 (Appendix C).

r k SB-1 SIT

                                                             .Page No. D-2

l l 2.2 Displacement Measurements The measuring devices were installed at varicus locations of the-Containment to measure displacements per CC-6232. These measure-ments include the following:

a. Radial Displacements of the Cylinder (Excluding Areas Adjacent to Equipment Hatch and Personnel Airlock) at four azimuths at Elevations 131.0', 114.58', 89.2', 59.4', 33.0', 9.5' (+),

(-) 25.0' and (-) 23.0' (only at azimuth 3500). Ref: Table D-1

b. Radial Displacements of the Cylinder Adjacent to the Equipment Hatch and Personnel Airlock- (at twelve points, four -equally spaced on each of three concentric circles).

Ref: Tables D-2 and D-4 Tables D-3 and D-5 provide diameter changes of the Equipment Hatch and Personnel Airlock respectively.

c. Vertical Displacements of the Cylinder near the spring line
 /           (at four approximately equally spaced azimuths) relat.ive to'the base mat.

Ref: Table D-6

d. Vertical displacements of the dome at the apex and two other approximately equally spaced intermediate points between the apex and the spring line.

Ref: Table D-7 The instrument numbers and locations shown on Tables D-1 through D-7 correspond to those identified in Figure 3 in Appendix C. i I SB-1 SIT Page No. D-3

            -_             _ __ . - - , __ ~ . _ . _ _ _     , - _ . _ _ - . _ _ _ . _ . _ _ . _ . - _               _ _ _ _ _ _ _ _ _

I 2.3 Concrete Crack Monitoring Cracks were monitored and mapped during the SIT at all locations shown on Figures 6, 7 and 8, and Sheets A6 through A9.1 in Appendix C. Areas shown on Sheets A6 through A9 were selected based on requirements of CC-6233. Sheet A9.1 shows additional crack mapping area selected based on pretest inspection (Ref: Section 4.3.4 in Appendix C). Location of concrete crack mapping areas are as follows:

1. Area near the spring line at Elev. 114.5' to 121.5', Azimuth, 1140 Area near the mid-height of the Cylinder at Elev. 42.5' to 49.5', Azimuth 109.70 Ref: Sheet A6
2. Area near the cylinder-to-base mat intersection at Elev. (-) 30.0' to (-)'23.0', Azimuth 1140 Ref: Sheet A7

[ ,

3. Area near the Personnel Airlock.

Ref: Sheet A8

4. Area near the Equipment Hatch.

Raf: Sheet A9

5. Selected areas near electrical penetration .between Elev. 0.0' to 8.0'.

Ref: Sheet A9.1 I l SB-1 SlT Page No. D-4 l

3 3.0 BASIS FOR PREDICTED AND ACCEPTABLE DATA 3.1 Displacements 3.1.1 Predicted Displacements Predicted series of displacements at selected locations of the Containment are listed on Tables D-1 through D-7. These data have been obtained f rom the Structural Analysis Group (SAG) Calculation Set No. SBSAG-34CS. Calc. Set SBSAG-34CS is based on information contained in the following documents:

1. SAG Reports SBSAG-7CS2 (Computer Runs #183 and 188) and SBSAG-7CS6 (Computer Run #1.13 on- Containment Axisymmetric Analyses.
2. Calc. Set No. CS-2'(Computer Runs #1, 2 and 3) - Analyses of Equipment Hatch.
3. Calc. Set No. CS-8 (Computer Runs #1, 2 and 3) - Personnel Airlock Analyses.

The predicted levels of displacements are based on the following considerations: I

a. Role of liner is not considered as a strength element.
b. The effects of creep and shrinkage are neglected.
c. The thermal growth of the Containment during the SIT is con-sidered to be minimal because of relatively stable wall temperature and_ previous SIT experience.
d. Concrete is assumed to have minimal tensile capacity. Concrete crack pattern is based on concrete tensile stress of 300 psi.

However, actual concrete tensile stress is much higher. based on actual concrete compressive strength at the time of SIT.

e. The predicted displacements are based on internal pressures only. Effects of prestress due to dead loads are -not con-sidered in predicting the vertical displacements.

The detailed analysis bases of the Containment are described in SB-1 FSAR Section 3.8.1, Docket No. 50-443 and also in Containment Design Report No. 9763.102-CDR-1. SB-1 SIT Page No. D-5

I 3.1.2 Acceptable Displacements All acceptable levels of displacements are 30% higher than the predicted values. Tables D-1 through D-7 list both the predicted and acceptable levels of displacements. The deflection recovery 24 hours af ter depressurization is 70% or more. The criteria of acceptable levels of displacements may be waived if recovery within 24 hours is greater than 80%. All instruments shall provide a minimum accuracy of + 5% of the maximum anticipated values. 3.2 Crack Widths The following criteria is obtained from UE&C Specification No. 9763.006-5-5, Section 5.2 (Appendix C): The prediction of crack pattern and widths is based on behavior of prototype containments. The predicted maximum crack widths at peak pressure in the membrane regions (excluding disconti-nuity regions around large openings) are expected to be 0.025 inch or less, spaced approximately 18 inches. Crack widths in the vicinity of large openings, such as equipment hatch and personnel airlocks may be greater. The acceptance criteria for ( cracks are as follows:

a. The maximum crack width at peak pressure of 60 psig is 0.035 inch averaged over a length of 20'-0; the minimum spacing is 15". These averages exclude crack patterns in the vicinity of large openings.
b. Crack widths after depressurization are predicted to be less than 0.01 inch.

e k SB-1 SIT Page No. D-6

                                                               -~                                                  ~

SIT PREDICTED AND ACCEPTABLE DATA TABLE D-1: Radial Displacements of Cylinder (Excluding Areas Adjacent to Equipment Hatcl and Personnel Airlock)' Displacements in Inch for Various Pr';ssures Instrument Location No. Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 psig (P) (A) (P) (A) (P) (A) (P) (A) (P) l (A) IG 1 131.0' 00 & 1800 0.223 0.29 0.447 0.581 0.67 0.87 0.897 1.166 1.031 1.34 IG 2 131.0' 900 & 2700 0.223 0.29 0.447 0.581 0.67 0.87 0.897 1.166 1.031 1.34 IG 3A 114.58' 00 0.21 0.28 0.42 0.55 0.62 0.81 0.83 1.08 0.96 1.25 IG 3B 114.58' 1800 0.21 0.28 0.42 0.55 0.62 0.81 0.83 1.08 0.96 1.25 IG 4 114.58' 900 & 2700 0.21 0.28 0.415 0.54 0.62 0.81 0.83 1.08 0.96 1.25 IG 5 89.2' 00 & 1800 0.211 0.274 0.421 0.55 0.632 0.822 0.842 1.09 0.967 1.257 IG 6 89.2' 900 & 2700 0.211 0.274 0.421 0.55 0.632 0.822 0.842 1.09 0.967 1.257 IG 7 59.4' 00 & 1800 0.197 0.256 0.393 0.511 0.59 0.77 0.786 1.022 0.898 1.167 IG'8 59.4' 900 & 2700 0.197 0.256 0.393 0.511 0.59 0.77 0.786 1.022 0.898 1.167 IG 9A 33.0' 380 0.21 0.28 0.40 0.52 0.592 0.77 0.791 1.03 0.957 1.25 IG 98 30.0' 2180 0.21 0.28 0.40 0.52 0.592 0.77 0.791 1.03 0.957 1.25 J (P) Predicted SB-1 SIT-t (A) Acceptable Page No. D-7 i

n . SIT PREDICTED AND ACCEPTABLE DATA TABLE D-1: Radial Displacements of Cylinder (Excluding Areas Adjacent to Equipment Hatch and Personnel Airlock) Displacements in Inch for Various Pressures i' Instrument Location No. Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 psig (P) (A) (P) (A) (P) (A) (P) (A) (P) (A) I IG 10 33.0' 1280 0.198 0.26 0.396 0.52 0.593 0.77 0.792 1.03 0.958 1.25 a

!      IG 11         31.5'      3080        0.198      0.26      0.396   0.52     0.593     0.77    0.792     1.03     0.958       1.25
;      IG 12          9.5'         420      0.19       0.25      0.381   0.50     0.572     0.75    0.766     1.0      0.894       1.16 IG 13          9.67'     1300        0.19       0.25      0.381   0.50     0.572     0.75    0.766     1.0      0.894       1.16 IG 14         10.0'      2220        0.19       0.25      0.381   0.50     0.572     0.75    0.766     1.0      0.894       1.16 IG 15          9.25'     3100        0.19       0.25      0.381   0.50     0.572 -0.75       0.766     1.0      0.894       1.16 i       IG 16      (-)25.0'           00(-)  0.025      0.04      0.053-  0.07     0.077     0.10    0.103     0.14     0.118       0.15 l      IG 17      (-)25.0'          900 (-) 0.025      0.04      0.053   0.07     0.077     0.10    0.103     0.14     0.118       0.15 i

IG 18 (-)25.0' 1800(+) 0.025 0.04 0.053 0.07 0.077 0.10 0.103 0. I'4 0.'118 0.15 l IG 19 (-)25.0' 2700(+) 0.025 0.04 0.053 0.07 0.077 0.10 0.103 0.14 0.118 0.15 } Ic 29 (-)23.0' 3500 0.037 0.048 0.074 0.096 0.112 0.146 0.149 0.194 0.172 0.224(1) i I l j (P) Predicted SB-1 SIT (A) Acceptable Page No. D-8 j (1) These values represent displacements computed for IG29 @ El. (-) 23.0'. Displacement l values shown for IG29 in Appendix I are different from these values because in Appendix I,

!           displacements computed for IG16 @ El       (-) 25.0' were considered as displacements for IG29.

1 j

              .                                                     -                                                ~

i SIT PREDICTED AND. ACCEPTABLE DATA TABLE D-2: Radial Displacements of Cylinder Adjacent to Equipment Hatch Displacements in Inch for Various Pressures Instrument Location No. Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 psig (P) (A) (P) (A) (P) (A) (P) (A) (P) (A) R 1 51.46' 1500 0.143 0.19 0.286 0.37 0.429 0.56 0.572 0.75 0.66 0.86 ! R 2 37.04' l6'1.70 0.185 0.24 0.37 0.48 0.555 0.72 0.739 0.96 0.853 1.11 R 3 22.62' 1500 0.153 0.20 0.306 0.40 0.459 0.60 0.612 0.80 0.707 0.92 R 4 37.04' 138.30 0.185 0.24 0.37 0.48 0.555 0.72 0.739 0.96 0.853 1.11-R 5 59.29' 1500 0.171 0.22 0.342 0.45 0.513 0.67 0.684 0.90 0.79 1.03 i R 6 37.04' 167.90 0.225 0.29 0.45 0.60 0.675 0.88 0.90 1.17 1.039 1.35 R 7 14.79' 1500 0.183 0.24 0.366 0.48 0.549 0.72 0.732 0.95 0.845 1.10 I ' R 8 37.04' 132.10 0.225 0.30 0.45 0.60 0.675 0.88 0.90 1.17 1.039 1.35 j R 9 72.04' 1500 0.123 0.28 0.426 0.56 0.639 0.83 0.851 1.11 0.982 1.28 R 10 37.04' 177.50 0.288 0.37 0.577 0.75 0.862 1.21 1.149 1.50 1.326- 1.72 R 11 (-)4.96' 1500 0.20~ 0.26 0.40 0.52 0.60 0.78 0.80 1.04 0.923 1.20 R 12 37.04' 122.70 0.288 0.37 0.577 0.75 0.862 1.12 1.149 1.50 1.326 1.72 (P) Predicted

  • SB-1 SIT (A) Acceptable Page No. D-9

SIT PREDICTED AND ACCEPTABLE DATA TABLE D-3: Equipment Hatch Diameter Change Displacements in Inch for Various Pressures Ins t rument No. Orientation 13 psig 26 psig 39 psig 52 psig 60 nsig (P) (A) (P) (A) (P) (A) (P) (A) (P) (A) IG 25 Vertical 0.016 0.021 0.032 0.042 0.047 0.061 0.063 0.082 0.073 0.095 IG 26 Horizontal 0.072 0.10 0.145 0.20 0.218 0.28 0.29 0.38 0.334 0.44 (P) Predicted SB-1 SIT (A) Acceptable Page'No. D-10

    ------ -e.a e.  .s--__-_#a. - _    -'+iw  - **+w-wa    6.a--he-      +- V -"'+ .' hNb2 j                                                                                                                %                                                 %

I SIT PREDICTED AND ACCEPTABLE DATA , TABLE D-4: Radial Displacements of Cylinder Adjacent to Personnel Airlock 1 1 Displacements in Inch for Various Pressures J Ins t rument Location j No. Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 psig (P) (A) (P) (A) (P) (A) (P) (A)- (P) (A) 1 R 13 33.75' 3150 0.191 0.25 0.383 0.50 0.576 0.75 0.77. 1.00 0.887 1.15 R 14 29.5' 318.50 0.19 0.25 0.383 0.50 0.576 0.75 0.77 1.00 0.887 1.15 lt R 15 25.25' 3150 0.196 0.26 0.392 0.51 0.588 0.77 0.783 1.02 0.904 1.18 i l R 16 29.5' 310.90 0.189 0.25 0.383 0.50 0.577 0.75 0.77 1.00 0.89 1.16 l l R 17 35.62' 3150 0.194 0.25 0.39 0.51 0.586 0.76 0.782 1.02 0.903 1.18 1 j R 18 29.5' 320.50 0.196 0.26 0.393 0.51 0.59 0.77 0.787 1.02 0.909 1.18

R 19 22.25' 3150 0.202 0.26 0.405 0.53 0.608 0.79 0.811 ,1.06 0.936 1.22 1

R 20 29.5' 3100 0.196 0.26 0.392 0.51 0.588 0.76 0.783 1.02 0.904 1.18-R 21 - 38.25' 3150 0.203 0.27 0.405 , 0.53 0.608 0.79 0.81 1.05 0.934 1.21 R 22 29.5' 322.10 0.203 0.27 0.405' 0.53 0.608 0.79 0. 8'l 1.05 0.935 1.22 R 23 20.75' 3150 0.205 0.27 0.412 0.54 0.62 0.81 0.827 1.08 0.955 1.24 i ! R 24 29.5' '307.90 0.203 0.27 0.405 0.53 0.608 0.79 0.81 1.05 .0.935 1.22 I

t l (P) Predicted SB-1 SIT f (A) Acceptable Page No. D-11 1

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SIT PREDICTED AND ACCEPTABLE DATA TABLE D-6: Vertical Displacements of Cylinder Near Spring Line Relative to Base Hat Displacements in Inch for Various Pressures Instrument Location __ No. Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 psig (P) (A) (PA) (A) (P) (A) (P) (A) (P) (A) IG 20 115.33' 00 0.31 0.41 0.61 0.79 0.92 1.20 1.22 1.59 1.41' l.84 IG 21 115.33' 1800 0.31 0.41 0.61 0.79 0.92 1.20 1.22 1.59 1.41 1.84 IG 22 117.33' 900 0.31 0.41 0.625 0.82 0.94 1.22 1.25 1.63 1.44 1.87 IG 23 117.33' 2700 0.31 0.41 0.625 0.82 0.94 1.22 1.25 1.63 1.44 1.87

                                                           ~

(P) Predicted SB-1 SIT (A) Acceptable Page No. D-13

                                                            -~

SIT PREDICTED AND ACCEPTABLE DATA TABLE D-7: Vertical Displacements of Dome Relative to Base Mat Displacements in Inch for Various Pressures P.T. Location Location Elev Azimuth 13 psig 26 psig 39 psig 52 psig 60 1sig (P) (A) (P) (A) (P) (A) (P) (A) (P) (A) IG 24b 152.0' 00 0.41 0.54 0.825 1.07 1.24 1.61 1.65 2.15 1.90 2.47 IG 24d 152.0' 00 0.41 0.54 0.825 1.07 1.24 1.61 1.65 2.15 1.90 2.47 IG 24a 182.4' 00 0.50 0.65 1.0 _1.30 l.50 1.95 2.00 2.60 2.31 3.0 IG 24c 182.4' 00 0.50 0.65 1.0 1.30 1.50 1.95 2.00 2.60 2.31 '3.0 IG 24 188.99' Apex 0.50 0.65 0.993 1.30 1.49 1.94 1.986 2.60 2.154 2.80 (P) Predict'ed SB-1 SIT (A) Acceptable Page No. D-14

CONTAINMENT STRUCTURAL INTEGRITY TEST SEABROOK STATION - UNIT 1 k APPENDIX E SIT /1LRT EQUIPMENT PROTECTION LIST l t l i . . , ,

i i l l 4

 .t-APPENDIX E SIT /ILRT EQUIPMENT PROTECTION LIST During the SIT, all pressure sensitive structures and equipment / components were adequately protected. The following Equipment Protection List was prepared by UE&C Engineering to insure that equipment / components were protected, vented or removed, and all such work was performed by UE&C Con-struction as directed by the STD.

I . t i l l l l l l SB-1 SLT Page No. E-1 l i I l l

                                                  ~                                                    -s Sheet 1 UNITED ENCINEERS & CONSTRUCTORS INC.

MECHANICAL EQUIPMENT / COMPONENT STRUCTURAL INTECRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. RECOP9 TENDED PROTECTION AIR COMPRESSOR SA-C-4A, B 310 O'-0" Secure (disconnect) power supply, depressurize air system, receiver & piping, open drain ubra & leave open for duration of test. After the test purge moist air from air piping before returning system to service. Supplement with 7/18/85 telecon with Cooper (attached). AIR DRYER 1A-D-2A, B 310* O'-0" Secure (disconnect) power supply, depressurize air and freon piping; leave valves open on air & freon piping. After test, recharge freon prior to putting air dryer back in service. High and low pressure f reon charging valves will have to be added since system is all brazed.

            *                                                        %                                                              .ms Sheet 2 UNITED ENGINEERS & CONSTRUCTORS INC.

f MECHANICAL SERVICES EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST i PROTECTION LIST - UNIT 1 i l l EQUIPMENT / EQUIPMENT / LOCATION

,  COMPONENT              _ COMPONENT
!     K. (E                     NO.         AZIMUTH             ELEV.                         RECOMMENDED PROTECTION CONTAINHENT STRUCTURE CAH-AC-1 A           70*               O'-0"        PCC water side in service during SIT.         Run fan at i   COOLING UNIT                                                              lowest speed.

CAH-AC-la 110* O'-0," PCC water side in service during SIT. Fan will not 3 run during test. Rack out breaker. CAH-AC-IC 150* O'-0" PCC water side in service during SIT. Run fan at lowest speed. I l CAH-AC-ID 210* O'-0" PCC water side in service during SIT. Fan will not j run during testing. Rack out breaker. i i CAH-AC-lE 250* O'0" PCC Water side in service during SIT.' Run fat at lowest speed. CAH-AC-IF 290* O'-0" PCC water side inservice during SIT. Fan will not run during test. Rack out breaker. i l CONTAINHEKr RECIRC. Call-F-8 280* 25'-0" Do not operate fans at a relative air density of j FILTER SYSTEM of greater than .1436 f/CF without repitching the blades ( 3 28 psig at ambient temp.). Vent filter ! housing by opening access doors, maintain filter j CS RECIRCULATION CAH-FN-3A 300, 25'-0" outlet dampers closed. Also see ECA 99/114411A for l FILTER additional protection on CAH-F-8 and ECA 99/114354A i

  • on CAH-FN-38.

? CAH-FN-38 300 25' i i I i

s -, Sheet 3 UNITED ENGINEERS & CONSTRUCTORS INC. NUCLEAR EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT / LOCATION l COMPONENT COMPONENT j NAME NO. AZIMUTH ELEV. REColttENDED PROTECTION PRESSURIZER RC-P-271 170* - 2 6 '-0" dELIEF TK PUMP Verify that bearing frame breather is open and free of dirt. RC DRAIN TK PUMPS WLD-P-33A&R 80 - 26'-0" Verify that bearing frame breather is open and free of dirt. HEAT EXCHANCER CC-E-153A & B 310*/250* - 26'-0" Vent entire system by assuring head tank is vented and valves 3" - CC-V395, 438, 439 and 422 are open. REFUELING FOOL SF-S-131 290* - 26'-0" STRAINER Open vent cock and clear dirt from opening.

REFUELING CANAL SF-P-272 280 - 26'-0"

] SKIMMER PUMP Verify that bearing frame breather is open and free of dirt. THERMAL BARRIER CC-P-322A&R 260* CLG. PUMP

                                                           - 26'-0"      Open inspection hole stop bearing frame and clear dirt from opening.

CNMT RECIRC SUMP CBS-TK-10A&R 280*/260*

                                                           - 26'-0"      Clear sump screens.     (Covered by ~ construction 1

cleanliness section of PT 37.1). ELEVATOR MM-MM-19 j 330* 25'-0" Verify that worm gear box has breather or open in-

                                        ;                                spection plug. Secure fan 37.

I l .i l 4

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            %                                                         .~                                                      -

Sheet 4 UNITED ENGINEERS & CONSTRUCTORS INC. CUCLEAR EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT / LOCATION [ COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. RECOMMENDED PROTECTION NEUTRON SHIELD N/A 0*-360 O'-0" For all (8) neutron shield panels. PANELS Remove bolts prior to test as shown on' attached sheet 11. Bolts to be reinstalled to spec. torque. See Note (1) J POLAR CANTRY - - - Verify that bearing frame or gear box has breather BRIDGE ASSY. or open inspection plug. See Note (2) POLAR CRANE - - - Remove during the test. DIGITAL READOUT t CALIVAR & OTHER Vent gear boxes and hydraulics as necessary. CONSTRUCTION CRANES NOTES: (1) Upon receipt of panels on site, inspection may suggest simpler protective measures. (2) Verify all gear boxes and hydraulics including the pendent drive are vented or remove fill plugs. Vent f reon f rom cab air conditioner. I l

                     +                                                           ~                                                          ,. .

I Sheet 5 UNITED ENGINEERS & CONSTRUCTORS INC. I&C EQUIPMENT / COMPONENT

,                                                             STRUCTURAL INTECRITY TEST l

PROTECTION LIST - UNIT 1 I EQUIPMENT / EQUIPMENT / LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. RECOMMENDED PROTECTION i VB SYSTEM $ LOOSE PARTS MONITOR VB-YT-6824-l&2 89* O' ( ) VB-YT-6825-l&2 35* - 44' (To be checked and tested af ter SIT l VB-YT-6826 thru 90*&270* - 26' (and ILRT. ] 6829-1,2 & 3 ( ! NI SYSTEM NI-NE-6690 & 320,* - 26' Ensure that the cable pulling fixture is sealed j EXCORE NEUTRON 6691 35 - 15' using teflon tape to the detector cable assembly. j DETECTION SYSTEM This is mandatory to protect the detector from moisture and other contaminents, or verify that the j detector cables are terminated to the detector. l CAS SYSTEM CAS-AT-8815 thru (Recalibrate the instrument af ter the completion of i 4 HYDROCEN ANALYZERS 8818-1,2,3 & 4 (the test. ( 3 CAS-AT-8815-1 250* - 26' ( NOTE: This is a preventive measure by the vendor l -2 75 - 26' ( due to lack of experience with the pressure l -3 80,, - 26' ( responae of the sensors. May be deleted I -4 150 - 26' ( for future ILRT's based on the results of CAS-AT-8816-1 180* - 26' ( the initial testing.

                                                    -2  165,            - 26'        (
                                                    -3  180*            - 26'        (
                                                    -4  200*            - 26'        (

CAS-AT-8817-1 185* - 26' ( l -2 178* 26' ( i -3 182* - 26' ( i -4 200* - 26' ( i 1 I t

       -                                                   ~                                                              ..

Sheet 6 UNITED ENGINEERS & CONSTRUCTORS INC. I&C EQUIPMENT / COMPONENT STRUCTURAL IlfrECRITY TEST

                  -                        PROTECTION LIST - UNIT 1                   ,

EQUIPMENT / EQUIPMENT / LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. RECOMMENDED PROTECTION __ CAS SYSTEM HYDROCEN ANALYZERS CAS-AT-8818-1 185* - 26' (Recalibrate the instrument after the completion of (Contd) -2 178, - 26' (the test.

                                -3  185*             -  26'       (
                                -4  200*             -  26'       (

WLD SYSTEM WLD-LSH/LSLH/ (Functional test is necessary after the completion LEVEL SWITCHES IN LSHH-6266 85, - 26' .(of SIT and ILRT. CONTAINMENT BLDC. 6267 350* - 44' ( SUMP A&B WLD-LSH/LSHH- 78* - 26' ( 1403 INST & SERV AIR IA-PSL-8024 310* O' Loosen the cover. Vent the switch to containment SYSTEM & 8026 atmosphere. PRESSURE SWITCHES IN INSTRUMENT AIR CAH SYSTEM CAH-PDSil-F8-1 --

                                                      + 25'         Perform functional test after SIT and ILRT.

CONT STRUCTURE FILTER UNIT RM SYSTEM o CAVITY BENEATH RM-RE-6529 5* - 40' Remove detector (Type RD-8). REACTOR VESSEL

b. MANIPULATOR CRANE RM-RE-6535 A&R 0* 28' Remove detector (Type RD-105 and indicator (RL-10).

RM-RI-6535 A&B l i i

q + - Sheet 7 UNITED ENGINEERS & CONSTRUCTORS INC. I&C EQUIPPENT/ COMPONENT STRUCTURAL IKTEGRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT / LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. REcoletENDED PROTECTION RM SYSTEM (Contd)

c. CONT. BLDC. SEAL RM-RE-6534 350* O' Remove detector (Type RD-10D).

INCORE SEAL TABLE

d. CAH SYSTEM RM-SKD-60 250* - 3' Isolate supply and return sample lines to skid by (RM-RM-6526) closing the manual isolation valves. (Covered by valve lineup in PT 37.1, skid outside containment.)

Additional "C.A." recommended protection actions for RM System o Open doors on RM-80 cabinets. o Remove all RC-10 digital indicators (there are more than two). o Unscrew plastic covers on alert and alarm lights. o RD-10 detectors need be only removed for initial SIT /ILRT. Future ILRT's at less than 50 psig need not remove these detectors. ASCO PRESSURE SWITCH WLD-PSH-1501 Equalize process line to containment atmosphere. This instrument is same as IA-PSL-8024 & 8026. BARKSDALE RC-PS-491 THRU Equalize to containment pressure. PRESSURE SWITCH 494 FIRE DETECTION No protective action is necessary, but be aware that SYSTEM the detectors will alarm on increasing air pressure and will be inoperable during the test. I

                                                      ~                                                        -

S 9 Sheet 8 UNITED ENGINEERS & CONSTRUCTORS, INC. ELECTRICAL EQUIPMENT / COMPONENT STRUCTUR.AL INTEGRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT / LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. REC 000 TENDED PROTECTION -__ LICHTINC FIXTURE Throughout Unscrew and loosen the cover, do not remove LAMPS bulbs on Ll6 fixtures. Containment Unscrew explosion proof covers on lighting on polar crane handrails (supplied with polar crane) (LIC type). Remove large lights underneath polar crane and bag in place or remove from containment. This is a precautionary measure to protect the reactor cavity from debris. L6, L6A, L7A, L78 fixtures are not sealed. The Ll6 fixtures are watertight and vaportight and covers must be loosened. Remaining lighting fixtures / lamps will not be affected by the SIT.

_ _ _ _ __ _ _ . . _ _. _ _ . _ . ~ . - . __ _ _ _. .- __ . _ . - ._ _._ _ _ . . _ _ . . . . _ . n ., .- Sheet 9 j UNITED ENGINEERS & CONSTRUCTORS, INC. i

 )          ELECTRICAL                                                                     EQUIPMENT / COMPONENT
  !                                                                                    STRUCTURAL IlffEGRITY TEST I                                                                                     PROTECTION LIST - UNIT I i

i j EQUIPMENT / EQUIPMENT / LOCATION j COMPONENT COMPONENT j NAME NO. AZIMUTH ELEV. REC 0 MENDED PROTECTION

,           LICHTING PANELS                       ED-m -163A                 320        (-) 26 ED-MM-1633                 180
;                                                 ED-m -1638                 170            0 ED-m-163E                  330 ED-m-163P                  320                           Punch hole through bottom of enclosure of j                                                  ED-m-163H                  170                           sufficient size to equalize the pressure ED-m -163K                 330                           transient.   (One time protection)

ED-m-163C 300 (+)25

!                                                 ED-m -163D                 120 ED-MM-163G                 160                           NOTE: #1 POWER PANELS                         ED-PP-8B                   320        (-)26              Punch hole through bottom of enclosure of j                                                                                                           sufficient size to equalize the pressure i                                                                                                           transient.   (One time protection)

! ED-PP-7A 320 0 I ED-PP-75 20 ED-PP-8A 170 NOTE #1 TERMINAL BOXES HMI,HM7 0 0 Punch hole through bottom of enclosure of Incore sufficient size to equalize the pressure transient. (One time protection) j Pressurizer X43, X45, X46,X47 100 (-)26 ! Pressurizer X44 100 0 l EC-X16 H 160 NOTE: #1 NOTE: #2 1 J l l 1

           .- s                                                                                                            --

Sheet 10 UNITED ENGINEERS & CONSTRUCTORS, INC. ELECTRICAL EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT / LOCATION COMPONENT COMPONENT NAME NO. AZIMUTH ELEV. REC 0letENDED PROTECTION __ SPEAKER-AMPLIFIER CM-3-1 thru 7 Throughout (1) Remove speaker-driver unit by removing l CM-3-12 thru 20 two wires and unscrewing the driver CH-3-22 Containment from horn. CM-3-24 thru (2) Remove handsets (total 5) by unscrewing CM-3-34 four screva and unplugging amplifier. CDTE: #1 Any conduit that penetrates an enclosure will contain sufficient free area to vent equipment during pressure transient test. Field walkdown must verify that conduit has not been sealed by Spec. 249-7 contractor. NOTE: #2 Installed procedures call for a 1/4 inch hole which is sufficient free area to vent equipment during pressure transient. Field walkdown mist verify if hole installed. i

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m --- - Sheet 12 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINGH0llSE (NUCLEAR) EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME ID/PO NO. AZIMUTH ELEV. RECOMMENDED PEDTECTION ROD POSITION NAH-340 , All P.C. boards and power supplies in the two DRPI INDICATION data cabinets are to be carefully removed by quali-DATA CABINETS fled electrical personnel and stored outside con-tainment before test. After tests are completed and humidity levels inside containment have normalized, all components are to be restored / reconnected to the original configuration. COMBINATION FIXED / NAH-360

  • The dehumidifier units within the system must be MOVABLE INCORE tur. icd off. Leave temporary space heaters on for DETECTION SYSTEM SIT.

COMPONENTS FLUX HAPPING SYS. FUEL HANDLING NAll-185

  • Fuel Transfer System Reactor Side Control Cabinet SYSTEM CONTROL Fil-RE-60 Verify that the three 1/2" dia. holes in cabinet CABINETS AND Fil-RE-5 bottom are clear (Ref. F.P. 55302). The cabinet REFUELING MACHINE heater circuit must be on and operate continuously during test. Holes are used for conduits.

Partially block open door for test.

  • Refueling Machine - Remove the control console during test and remove the video cameras f rom the bridge and trolley. Secure air compressor and vent.
  • NOTE: Unless otherwise indicated, this procedure must be reversed af ter completion of S1T & ILRT Tests to restore systems to their original condition.
                                                                                                +

Sheet 13 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINGHOUSE (NUCLEAR) EQUIPMENT / COMPONENT STRUCTURAL IKrECRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME ID/PO NO. AZIMUTH ELEV. RECOMMENDED PROTECTION PRESSURIZER RC-TK-11 Vent to containment atmosphere. RELIEF TANK

  • Open RC-V-152 and remove blind flange.

ACCUMULATOR SI-TK-9A Vent to containment atmosphere

  • Open SI-V-9, FV-2475 & FV-2476 SI-TK-98 Vent to containment atmosphere
  • Open SI-V-29, FV-2482 & FV-2483 SI-TK-9C Vent to containment atmosphere
  • Open SI-V-44, FV-2477 & FV-2486 i

SI-TK-9D . Vent to containment atmosphere

  • Open SI-V-59, FV-2495 & FV-2496 l

REACTOR RC-P-IA Typ. for RC-P-1A, B. C & D COOLANT PUMP RC-P-1B After completion of SIT the polarization index of the RC-P-IC stator insulation must be checked per Section 5.1.2 ! RC-P-ID  ; of the instruction manual (Ref. F.P. 54502). Test voltage should be 2500 Volts DC, minimum acceptable P.I. is 2.0. If measured P.I. is less than 2.0 dry windows per section 5.4.6 of the manuall and retest. _. .i___-__...._

  • See note on Sheet 12.

w ~ .~ l Sheet 14 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINCHOUSE (NUCLEAR) EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT I 1 1 EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME ID/PO NO. AZIMUTH ELEV. REC 000(ENDED PROTECTION 3 . i PRESSURIZER RC-E-10 Vent to containment atmosphere .

  • Open RC-V-127 i (Note: Preesurizer heater resistances may not be accurate if measured during high humidity conditions)

{ STEAM GENERATOR RC-E-IIA Primary side is vented through RCS. Secondary side . RC-E-IIB not to be vented. RC-E-IIC - RC-E-11D HYDROCEN CGC-MM-284A The following procedure should be followed after com-RECOMBINER CCC-MM-2848 pletion of test but before energizing units. Deter-mine the resistance to ground values using 250 Volts DC for each phase, for each recombiner (including interconnecting cabling) at the power supply. All resistance values should be in excess of 30 K Ohms before energizing the recombiner. .lf the minimum values determined are above 30 K Ohms but below 100 K Ohms, tiien energize recombiners to 1200 Deg. F for

8 hours to drive moisture from heating elements.

i Allow recombiner to enM to approximately ambient temperature and repeat iesistance test. New resist-j ance values should be in excess of 100 K Ohms. i

  • See note on Sheet 12

3 Sheet 15 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINCHOUSE (NUCLEAR) EQUIPMENT / COMPONENT STRUCTURAL IIRECRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME ID/PO NO. AZIMUTH ELEV. RECOMMENDED PROTECTION FUEL TRANSFER FH-RE-60 See fuel handling system control cabinets NAH-185. ELECTRICAL CONTROL (F.P. 55302) HYDRAULIC POWER UNIT MANIPULATOR CRANE FH-RE-5 See fuel handling system control cabinets & refueling

          &               (F.P. 54057)                            machine. NAH-185 FUEL LIFTING HECH.

l l

q Sheet 16 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINGHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL IfffEGRITY TEST PROTECTION LIST - UNIT 1 i

   -EQUIPMENT /            EQUIPMENT       LOCATION COMPONENT              COMPONENT NAME                   NO. AREA             ELEV.                RECOMMENDED PROTECTION RC-E-10              (RC) LT-459 C8              0'-0"                Maintain in normal lineup PRESSURIZER                     CI-0 (RC) LT-460 C8               0'-0" CI-0 (RC) LT-461 C8               0'-0" CI-0 (RC) LT-462 C8               0'-0" CS-0 RC-P-ID             (CS) PT-150 IR-8             0'-0"               Maintain in normal lineup.

NO. ! SEAL CS-0 Inspect, dry and calibrate if saturated PRESS conditions exist during the test. (CS) PT-151 IR-7 0'-0" Loosen plastic covers on Bartons for CS-0 SIT only. (Not necessary for ILRT's in service.) (CS) PT-152 IR-6 0'-0" CS-0 RC-P-IA (CS) PT-153 IR-Il O'-0" NO. I SEAL CS-0 PRESS If

s . .., Sheet 17 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINCHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAMC NO. AREA ELEV. RECOP9 TENDED PROTECTION RC-E-IIA (FW) FT-512 IR-ll O'-0" Maintain in normal lineup STM CEN CS-0 (Causes a containment leak if vented (FW) FT-513 C-16 0'-0" to steam side. These are containment CS-0 boundary.) RC-E-IIB (FW) FT-522 IR-6 0'-0" STM CEN CS-0 (FW) FT-523 IR-6 0'-0" CS-0 RC-E-!!C (FW) FT-532 IR-7 0'-0" STM CEN CS-0 (FW) FT-533 IR-7 0'-0" CS-0 RC-E-IID (FW) FT-542 IR-8 0'-0" STM CEN CS-0 (FW) FT-543 IR-8 0'-0" CS-0 -

x _ _ , Sheet 18 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINCHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT 1 EQUIPMENT /. EQUIPMENT LOCATION COMPONENT COMPONENT NAME NO. AREA ELEV. RECOMMENDED PROTECTION , , , , RC-E-IIA (FW) LT-517 C-17 0'-0" Maintain in normal lineup SG NRW RNG CS-0 (Causes a containment leak if vented. (FW) LT-518 These are containment bounda ry. ) (FW) LT-519 RC-E-IIB (FW) LT-527 C-5 CS-0 i (FW) LT-528 (FW) LT-529 l RC-E-!!C (FW) LT-537 C-5 26'-0" CS-26 (FW) LT-538 C-5 26'-0" ! CS-26 (FW) LT-539 IR-7 0'-0" i CS-0 RC-E-IID (FW) LT-547 IR-8 0'-0" i SG NRW RNG CS-0 l ? (FW) LT-548 I (FW) LT-549

Sheet 19 UNITED ENGINEERS & CONSTRUCTORS INC.

       - WESTINGHOUSE (I&C)                                 EQUIPMENT /C0!iPONENT STRUCTURAL IlfrECRITY TEST PROTECTION LIST - UNIT 1 1

i EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME NO. AREA ELEV. RECOMMENDED PROTECTION RC-E-10 (RC) PT-455 C-8 0'-0" Maintain in normal lineup PRZR CS-0 (RC) PT-456 0'-0" (RC) PT-457 (RC) PT-458 RC-P-ID (CS) FT-154 C-Il 26'-0" C* Maintain in normal lineup LO RNG LKCE CS-26 Inspect, dry and calibrate if saturated IC (CS) FT-155 C* conditions occur during the test. IB (CS) FT-156 C* 2A (CS) FT-157 C* RC-P-ID (CS) FT-158 C-Il 26'-0 C HI RNG LKCE CS-26 , 2C (CS) FT-159 C IB .(CS) FT-160 C 1A (CS) FT-161 C EXCESS LETDN (CS) PT-124 C-Il 26'-0" C OUTLET PRESS CS-26 RC-E-IIA (FW) LT-501 C-16 26'-0" A Maintain in normal lineup j .SG WIDE RNG CS-26 ! (Containment boundary instrumentation)

               !!B                (FW) LT-502                                     A 11C               (FW) LT-503                                     A j                llD               (FW) LT-504                                     A                                        .

j

  • Loosen covers on Bartons for SIT only. (Not necessary for future ILRT's.)

I

S ., _

                                                                                                                                                         ~

Sheet 20 UNITED ENCINEERS & CONSTRUCTORS INC. WESTINCHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL INTECRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME NO. AREA ELEV. RECOMMENDED PROTECTION RC-E-IIA (FW) LT-551 C-16 26'-0" Maintain in normal lineup LOOP 1 CS-26 (Containment bounday) 118 (FW) LT-552 C-3 CS-26

                                                                          !!C                               (FW) LT-553                       C-7 CS-26
                                                                          !!D                               (FW) LT-554                       C-13 CS-26 RC LOOP 1                                (RC) FT-414                        C-15                                 Maintain in normal lineup CLDL FLOW                                                                    C-26 Inspect, dry and calibrate if saturated (RC) FT-415                         C-17                                 conditions occur during the test.

CS-26 (RC) FT-416 C-17 CS-26 RC LOOE 2 (RC) FT-424 C-3 CLDL FLOW CS-26 RC LOOP 3 (RC) FT-425 C-3 CLDL FLOW CS-26

She:t 21 UNITED ENGINEERS & CONSTRUCTORS INC. WESTINCHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL INTEGRITY TEST PROTECTION LIST - UNIT I EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT NAME NO. AREA ELEV. RECOMMENDED PROTECTION RC LOOP 2 (RC) FT-426 C-4 26'-0" Maintain in normal lineup CLDL FLOW CS-26' - ~ ~ ~ Inspect, dry and calibrate if saturated RC LOOP 3 (RC) FT-434 ) C-8 conditions occur. CLDL FLOW (RC) FT-435 ) CS-26 (RC) FT-436 ) RC LOOP 4 ,(RC) FT-444 C-14 CLDL FLOW CS-26 (RC) FT-445 C-13 CS-26 (RC) FT-446 C-13 CS-26 RC TK-ll (RC) LT-470 C-8 PRZR RELF TK CS-26 (RC) PT-469 C-8 CS-26 ACCUM TK 9A (SI) LT-950 IR-10A

  • 9A (SI) LT-951 CS-26
  • 98 (SI) LT-952 IR-10B
  • 98 (SI) LT-953 CS-26
  • 9C (SI) LT-954 IR-10C
  • j 9C (SI) LT-955 CS-26
  • 9D (SI) LT-956 IR-10D
  • 90 (SI) LT-957 CS-26 *
  • Swing open covers on Bartons for SIT only (not required for future ILRT's)
  'i Sheet 22 UNITED ENGINEERS & CONSTRUCTORS INC.

WESTINGHOUSE (I&C) EQUIPMENT / COMPONENT STRUCTURAL I!(fECRITY TEST

.                                                                     PROTECTION LIST - UNIT 1 i

EQUIPMENT / EQUIPMENT LOCATION COMPONENT COMPONENT 1 NAME NO. AREA ELEV. RECOMMENDED PROTECTION ACCUM TK 9A (SI) PT-960 IR-10A 26'-O" ' Haintain in normal lineup 9A (SI) PT-961 CS-26 98 (SI) PT-962 IR-10B . Inspect, dry and calibrate if saturated 98 (SI) PT-963 CS-26 conditions occur. i 9C (SI) PT-964 IR-10C 9C (SI) PT-965 CS-26 (SI) PT-966 IR-10D 9D 9D (SI) PT-967 CS-26 i l l

j Ma'cMMicDL 6Ub0 f ffpCHMfNT 70 /GUIHffM 7lCo MPdNfMT M 0ff Cfl0N L os r Public Service Company of New Hampshire l JMaff Z 3 l j TELEPHONE CONVEI ~ - TION MEMORANDtN i i Conversacion with: Art Hawk of (Firm): Cooper Date: 7/18/85 1-215-258-5351 Time. 1100 Ac (Address):

Subject:

ILRT Pressurization Originated by: T dimeneemd with Art nur ennearna with enneminnene inetr*nnen emei nn Anv4 ne ehm TT WT nemannei rmeine en 60.1 neie. Are in f acemed me ehme ehm f at i ner4 n e ehan1d neene en nraelude any d -- em . The Smevies Ai r from SA-4A and 45 in cone =4n==at should be vented. The distance piecee which provida distance between the cylinder and crank should have the plugs removed on either the top or bottom drain. Both suction and discharge lines should be vented. With the system vented then no in-strumentation problems will exist. l .. . I Signed: // 2

                                                                                         >-._ _f-j Danie d Trautumn
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t t } CONTAINMENT STRUCTURAL INTEGRITY TEST SEABROOK STATION - UNIT 1 1 ( . APPENDIX F i TECHNICAL PROCEDURE NO. TP-13

                                                                                            -STRUCTURAL INTEGRITY TEST l

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