ML17263A465

Radial Displacement & Rebar Strain Measurements for EWR 5181,Rev a

ML17263A465
Person / Time
Site:	Ginna
Issue date:	05/17/1993
From:	Bermudez R, Wallace L SENSING SYSTEMS CORP.
To:
Shared Package
ML17263A464	List: ML17263A463 ML17263A465
References
500167-7, NUDOCS 9311160412
Download: ML17263A465 (168)

Text

SENSING SYSTEMS CORPORA TIO TRANSDUCERS ANDSERVICES VENDOR'S DOCUMENT REVIEW go~~ yfr.7+87 5~4~~ 4~.f 1

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ApprovedIMf~y-proceed 2

Approved Sumit Cinol doc't.

Mfg. moy proceed Approved ~cept os noted Make changes and submit finol doc't. Mfg. moy proceed os approved 4

Not approved Correct and resubmit.

5 Review not required Mfg. moy proceed SEEvV Approval of this d ment does not relieve supplier from full co iance th tract ar purchase erder requirements.

Date OCH STER GAS & ELECTRIC CORP.

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ROCHESTER, N.Y.

R.E.

GINNA NUCLEAR POWER PLANT RADIAL DISPLACEMENT AND REBAR STRAIN MEASUREMENTS FOR EWR 85181 Revision A TECHNICAL REPORT 50016-7 May 17, 1993 CONSTRUCTION LIMITED CONSTRUCTION:

AS NOTED PRELIMINARY NOT FOR CONSTRUCTION BIDDING P RPOSES Copy No.

2 E

RELEASED FOR NGR P.O. BOX50180 NEWBEDFORD, MASSACHUSETTS 02745 0006 TELEPHONE: (508) 992 0872 FAX:(508) 990 8930 9311160412 931111 PDR ADOCK 05000244 P

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Technical Report 50016-7 R.E.

GINNA NUCLEAR POWER PLANT RADIAL DISPLACEMENT AND REBAR STRAIN MEASUREMENTS FOR EWR 55181 Revision A TECHNICAL REPORT 50016-7 May 17, 1993 Written By:

Approved By:

card Be llQe LaVerne F. Wallace 11

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Technical

Report, 50016-7 TABLE OF CONTENTS Item Descri tion Pacae

1.0 INTRODUCTION

2.02.1 2.2 INSTRUMENTATION 1

Sensor Instrumentation and Installation 2

" Techniques Recording Instrumentation 5

3.03.1 3.2 TEST Test Procedure Data Reduction and Analysis 4.0 5.05.1 5.2 RESULTS DISCUSSION OF RESULTS Radial Growth Results Rebar Stress Results 12 12 12 APPENDIX A

,APPENDIX B APPENDIX C APPENDIX D SPEC IFICATIONI PROCEDURES AND MATERIAL PROVIDED BY ROCHESTER GAS AND ELECTRIC CO.

RAW DATA CALIBRATION CERTIFICATES TEST PERSONNEL 3.3.3.

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Technical Report 50016-7 LIST OF TABLES Table Pacae Radial Growth Versus Pressure.

Rebar Stress Versus Pressure.

LIST OF FIGURES

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t Radial Displacement 40 42'zimuth.

A Radial Displacement 166 07'zimuth.

Versus Elevation.

Versus Elevation.

Pacae 10 Radial Displacement Versus Elevation.

260 00'zimuth.

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Technical Report 50016-7 1 0 IHTRODUCTIOH Sensing Systems Corporation was contracted by Rochester Gas Electric Corporation (RGGE) under Purchase Order No. CP-49467-C-RD to conduct radial displacement measurements at the R.E.

Ginna Nuclear Power Plant in Ontario, New York.

Test preparations and measurements were conducted during the period from March 31 to April 15, 1993.

In addition to the radial displacement measurements, rebar strain gage measurements were added to the scope of the work prior to start of the test.

Radial displacement measurements and strain gage measurements were conducted during the first Integrated Leak Rate Test (ILRT) pressurization-depressurization cycle.

These measurements were obtained at pressure plateaus of 0,

15, 35 and 0 psig.

In addition, strain gage measurements and radial displacements at two locations were obtained at 25 psig.

This report describes the procedures followed before and during the tests and the results of the data acquisition program.

Documentation provided by RGGE regarding the ILRT may be found in Appendix A.

2 0 IHSTRUMEHTATIOH The response of the Containment Building were measured during the first ILRT pressurization-depressurization cycle by the following methods:

a. Measurement of displacements.

b. Measurement of rebar strain.

Two distinct sets of equipment were setup to acquire the desired data.

This section describes the equipment and the configurations used for effecting radial displacement and strain gage measurements.

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Technical Report 50016-7 2.1 Sensor Instrumentation and Installation Techniques:

All sensors and instrumentation were installed in accordance with the locations stipulated in RGGE s Bid Specification CE-165, Rev 0, 9/25/92.

This document may be found in Appendix A.

2.1.,1, Optical Tooling Scales:

Optical scales and jig transits were used to measure cylinder wall radial displacement.

Optical tooling scales were mounted by RGGE personnel directly to the containment building at the prescribed locations.

The scales were positioned to be perpendicular to the wall surface and to the jig transit line of sight.

Two fixed reference-targets were used for each of the three optical scale azimuths to establish the plane to which the radial growth was referenced.

2.1.2 Scale Locations:

Three sets of four. displacement measuring scales were located at three azimuth locations around the Containment Building as

,follows:

Elevation Azimuth 260'-0" 288'-0",

315'-0" 337'-0" 40'42'i 166 07'I 260'00'0 42 g

166 07 f 260 00 40 42 g

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260 00 40 42 g

166 07 g

260 00 2.1.3 Jig Transit Locations:

t Each Jig Transit was positioned on top of a tripod by using A 3.5-8 inch adaptor.

Each Jig Transit was located at one of the prescribed azimuth locations as follows:

40 42'zimuth Location:

The Jig Transit was positioned above penetration number I-90H-P located in the Intermediate Building (North)

Basement Floor

Level, elevation 253'8".

166'07'zimuth Location:

The Jig Transit was positioned above penetration number A-57-P located in the Auxiliary Building Operating Floor Level, elevation 271'0".

260'00'zimuth Location:

The Jig Transit was positioned above penetration number I-16-P located in the Intermediate Building (West)

Basement Floor

Level, elevation 253'6".

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Technical Report 50016-7 2.1.4

.Target Locations:

Two ta'rgets were installed at each Azimuth location to establish a reference plane.

Their locations were as follows:

40'42'zimuth Location:

The two targets were located in a vertical plane at right angles to the 40'42'adial line and 7.25 inches from the containment surface.

The first and p'rimary target was placed on an existing bracket attached to a steel column northwest of the transit position and at a sight distance of 72 inches.

The second target was placed on the inside surface of the east wall of the intermediate building and at a sight distance of 38 inches.

166'07'zimuth Location:

The first target was located on the vertical concrete wall between the Auxiliary Building Operating Floor level and the fuel transfer pool.

It was located approximately 30 ft.

from the

transit, 8 ft. from the containment wall and 7 ft. above the jig transit floor level.

The second target was located directly below the 260'-0" scale on the next floor level and on the same azimuth (166 07') line as the scales and the Jig Transit.

260'00'zimuth Location:

The first target was located on a unistrut member approximately 15 ft.

from the Jig

Transit, 3 ft. from the containment wall and 1 in. above the floor.

The second target was placed on a

concrete base approximately 30 ft. from the Jig Transit, 10 ft. from the Containment Wall and 3 in. above the floor.

2.1.5 Rebar Strain Gages:

The original 1969 rebar strain gages and cables were in place prior to the start of the 'current test.

A visual inspection and electrical check-out program was conducted prior to the test to determine and select fully operational strain gages.

Eight rebar strain gage installations were selected for monitoring during the test based on the results of the inspection program.

Four rebar were selected from the equipment hatch locations, two were selected from the dome area and two from the cylinder wall area.

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Technical Report 50016-7 The rebars were originally (1969) instrumented with two tee strain'gages wired into a full Wheatstone bridge.

The gages were equally spaced on the circumference of the rebar to indicate average strain.

The function of the lateral gages was to, compensate for temperature effects and to provide additional bridge sensitivity proportional to Poisson's ratio.

Additional cable lengths were spliced to all strain gage channe'ls and routed to the outside equipment hatch enclosure.

This permitted all rebar strain gages to be read from the same locat'ion.

2.1.6 Rebar Strain Gage Locations:

The exact location of each rebar ',strain gage, is detailed below.

The same location'number used in the original report is also used in this document for direct comparison of stress values.

The letter V denotes the Vertical or Meridional direction'and the. H denotes the Horizontal or Hoop direction.

All dome and cylinder wall rebars were vertical bars.

Location No.

31V Elevation 2 8 1 /8" Notes 16 ft.

(CCW direction) from Equipment Access Opening along horizontal axis.

31H 32V 2 8 1 /8" 281 /8" Same as above.

21 ft.

(CCW direction) from Equipment Access Opening along horizontal axis.

32H 42 '.

49 54 58 281 7V-336'2" 342'2" 346'8" 350'2" Same as above.

Cylinder Wall, Azimuth 30 Cylinder Wall, Azimuth 150'.

Dome Junction, Azimuth 30 Dome Junction, Azimuth 150

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Technical Report 50016-7 2.2 Recording Instrumentation:

2.2.1 Jig Transits:

.The wall radial growth data were recorded using two KGE and one Brunson Jig Transits with optical micrometers.

Data were recorded by first leveling the instrument, aligning the instrument with the ground reference targets and then sighting the individual scales.

Scale data were taken by reading the inches and tenths of inches from the scale graduations.

Hundredths and thousandths of an inch were reads using the optical micrometer.

A total of 3-5 readings were recorded over a

10-20 minute period of time while re-checking the instrument setup.

The average of all readings was recorded on the data sheet.

2.2.2 Rebar Strain Gages:

All Rebar Strain Gage data were recorded by individually connecting each channel to a Vishay P-3500 digital strain indicator.

Each reading was monitored for approximately 30 seconds to one minute to determine their stability prior to recording its value.

3.0 TEST 3.1 Test Procedure:

3.1.1 General

The radial displacement and rebar strain measurements were performed in conjunction with the 1993 Outage Integrated Leak Rate Test.

Two different pressurization-depressurization cycles were necessary for. the successful completion of the ILRT.

All measurements reported in this document were performed during the first pressurization-depressurization cycle.

3.1.2 Preparations

All test personnel were on site several days prior to the start of the test.

Checks were made and daily readings were taken by the test personnel to insure that all instruments and equipment required for the 'test were installed and operating satisfactorily.

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Technical Report 50016-7 3.1.3 Zero Pressure:

Test personnel acquired data at zero psig for a period of five days prior to the start of the test.

The data were evaluated for consistency and accuracy.

The last zero psig data prior to the start of the test were taken 15 minutes prior to starting the first pressurization-depressurization cycle.

3.1.4 Pressurization and Depressurization:

Test data were recorded after pressurization was increased to each test pressure level and held for a

period of approximately one hour to allow time for obtaining the measurements.

Radial displacement and rebar strain measurements were taken in this manner at 0,

15, 35 and 0

psig.

Additional radial displacement readings (at two locations only) and rebar strain readings were taken at 25

'psig and 26 psig respectively.

The two locations for which displacement data were obtained at 25 psig were the 40'42'nd 166'07'zimuths.

The additional readings were taken without the one hour hold.

3.2 Data Reduction and Analysis:

3.2.1 Optical Data:

Radial displacement growth at each scale has been determined from the jig transit readings by subtracting the scale reading recorded at 0 psig from the readings taken at each of the test pressure levels.

3.2.2 Rebar Strain Gage Data:

The rebar strain data at each location has been determined from the P-3500 readings by subtracting the value recorded at 0 psig from the readings taken at each of the test pressure levels.

Rebar stress values in pounds per square inch (psi) have been calculated from the strain data and using a Poissons ratio of 0.30 and a modulus of elasticity of 30 x 10 psi.

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Technical Report 50016-7 4.0 RESULTS All results are presented in the form of tables or figures.

Radial Growth values versus Pressure are presented in Table I whereas Rebar Stress values versus Pressure are shown in Table II.

Graphical representations of Radial Displacement versus Containment Building Elevation are shown on Figures 1 through 3.

Raw data may be found in Appendix B.

TABLE I.

Radial Growth Versus Pressure.

Elevation Azimuth Pressure (psig) 260'88'15'37'0o42'5 25 35 0

0.032 0.073 0.117

-0.002 0.040 0.097 0.150 0.000 0.049 0.119 0.184 0.006 0.041 0.068 0.106 0.003 166 07'5 25 35 0

0.037 0.099 0.158 0.002 0.051 0.124 0.191

-0.002 0.047 0.112 0.174

-0.003 0.015 0.040 0.070

-0.010 260OOO'5 35 0

0.031 0.144

-0.003 0.035 0.140

-0.001 0.019 0.124

-0.003 0.005 0.045

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Technical Report 50016-7 TABLE ZI.

Rebar Stress Versus Pressure.

Rebar Location Rebar Stress (psi)

Pressure 15 (psi) 26 (psi) 35 (psi) -,;

0(psi) 31V 31H 32V 32H 49 54 58 750 620'110 1820 890 1030 1030 770 1800 3920 1100 1750 1320 1280 2560 6880 1520 2000 30

-30 210 10

-700 100 NOTES:

1.

Rebar Stress Values Calculated Based on E = 30 x 106 psi and p = 0.30.

2. Measurements on Rebar Location 49 were drifting during monitoring period.

Technical Report 50016-7 40'42'zimuth Kiev.

343'-2 II Kiev.

330'-8" E le v.

231'-8" 310 270 250 I

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-0.05 0.00 0.05 0.10 0.15 0.20 0.25 0.30 Displacement (in.)

Figure 1.

Radial Disp. Vs. Elevation

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Technical Report 50016-7 10 166 07'zimuth Elev.

.330'-8" Kiev.

2313-8" E le v.

343'-2 II 330 310 270 I

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Figure 2.

Radial Disp. Vs. Elevation

Technical Report 50016-7 Z60'00'zimuth N

Ele v.

343'-2 Llev.

330'-8" I

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-0.'f0 -0.05 0.00 0.05 O.IO 0.15 0.20 0.25 Displacement (in.)

Eigure 3.

Radial Disp. Vs. Elevation

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Technical Report 50016-7 12 5

0 DISCUSSION OF RESULTS 5.1 Radial Growth Results:

The accuracy of the radial growth data is estimated to be within 0.005 to 0.010'nches.

These figures are based on the precision of the equipment used and the sight. distances for the individual scale locations.

This accuracy is consistent with the original test results conducted in 1969..

5.2 Rebar Stress Results:

The accuracy of the rebar stress data is estimated to be within

+ 500 to 1000 psi.

This is a conservative estimate based primarily on the age of the strain gage installations which were installed in 1968.

It is also based on the electrical insulation resistance readings to ground recorded prior to the ILRT.

The actual accuracy of the stress data may be better than estimated.

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Technical Proposal P-50016-7 APPENDIX A SPECIFICATIONS PROCEDURES AND MATERIAL PROVIDED BY ROCHESTER GAS AND ELECTRIC CO.

Documents:

Containment Building Radial Displacement Measurement Services.

R.E.

Ginna Nuclear Power Plant Specification CE-165.

Integrated Leak Rate Test Containment Structural Inspection Procedure No. RSSP-6.5 Containment Integrated Leakage Rate Test-Procedure No. RSSP-6.0.

Consumable Material Control System.

Restricted Use Permit No. 93:104 Product: Loctite Fast Cure Epoxy 45.

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0" ROCHESTER GAS AND ELECTRIC CORPORATION Containment Building Radial Displacement Measurement Services R. E. Ginna Nuclear Power Plant CE-165 Issued By Rochester Gas &, Electric Corp.

Nuclear Engineering Services

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9/25/92 Issue for Bidding

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'on Engineer Bid SpeciTication CE-165 Page ii Rev 0 9/25/92

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2 "Proposal Form I" Drawing Index id SpeciTication

~ CE-165 Page iii Revision 0 9/25/92

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8 IN RADI D

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7~If Division I - Job Requirements Attachments

¹1)

Proposal Form I

¹2)

Drawing Index Sheet d Specification CE-165 Page 1 Revision 0 9/25/92

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NTAINME B ILDI RADIALDI PLA EME MEA EME VI R. E. GINNANUCLEAR POWER PLANT I

T BIDDE 1.0 R

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2.0 The Bid Proposal shall not be considered unless it includes Proposal Form I, consisting of the accompanying form properly and completely filled out.

The Bidder shall use the same format and page numbering when submitting the Bid Proposal.

PRI E INF RMATI The base price shall appear only where specified in the Proposal Form I, and shall not appear elsewhere in the Bid Proposal.

Other price information, such as options and alternates, shall be given as a price addition to or deduction from the base price as specified in the Proposal Form I, or attached thereto.

Unit Prices (if any) shall be as specified in Proposal Form I. Price information shall not be included in the Bid Proposal transmittal letter or in the Bidder s technical or other nonprice data information.

3.0 MPL F

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3.1 0

4.0 Bidder is hereby notified that it is Rochester Gas and Electric's intention that the Bid Proposal shall be complete in order to avoid extras to the Contract price.

Bidder shall include in the Bid Proposal, pricing for all work which is indicated or implied in the Bid Documents, whether or not such work is fully detailed.

Bidder's proposal will not be considered unless all items in the proposal forms are completely filled out.

Bidder shall use a "Not Applicable-(N/A)" if the item does not apply.

L ATI 4.1 4.2 The R. E. Ginna Nuclear Power Plant is located 15 miles northeast of Rochester, New York, on the south shoreline of Lake Ontario.

I AllBid Proposals shall be returned to RG&E bg the due date of Friday, October 30, 1992 to the following mailing address (Corporate Offices):

Mr. Gregory J. Fuller Department Manager and Purchasing Agent Materials Management Department Rochester Gas & Electric Corporation 49 East Avenue Rochester, NY 14649 Attention: Robert J. DiBaudo d Specification CE-165 Page 2 Revision 0 9/25/92

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5.0 5.1 5.2 6.0 QENERAL The R. E. Ginna Nuclear Power Plant is a single unit site owned and operated by the Rochester Gas and Electric Corp.

The Unit incorporates a Westinghouse design 2-loop Nuclear Steam Supply System and Turbine-Generator rated at 490 megawatts electrical.

The R. E. Ginna Nuclear Power Plant expects to conduct it's annual refueling outage of the Ginna plant from March 19, 1993 thru to May 8, 1993.

The work described in this document must be performed during the last two (2) weeks of April 1993, prior to the restart of the plant.

PE WR 6.1 Containment Building Radial Displacement Measurements.

The Contractor shall supply all equipment, materials, personnel, and procedures required to collect, check, and record the radial growth and rebound of the Containment Building during RG&E's performance of the structure's Integrated Leak Rate Test (I.L.R.T.).

Three (3) sets of four (4) displacement measuring scales are located at three (3) azimuth locations around the Containment Building, as listed below:

E~lev i n 260'-0" 288'-0" 315'-0" 337'-0" Azim~

40'42', 166'07',

260'00'0'42',

166'07-',

260'00'0'42',

166'07'60'00'0'42',166'07',

260'00'ptical alignment scales whose markings are calibrated to be read to within + 0.001 inches willbe mounted at each location.

A full set of displacement measurements willke recorded at each of five (5) pressure levels (i.e., 0, 15, 35, 15, and 0 psig.).

The building pressure shall be held constant for approximately one (1) hour at each pressure while the structural data is being recorded.

Time durations at each pressure level may be extended for I.L.R.T.

requirements.'ressurization and depressurization rates will not exceed five (5) psig per hour.

The acquisition of structural data shall not interfere with either the performance of the I.L.R.T.

or the acquisition of I.L.R.T. data.

The actual method used to obtain radial displacement data shall be subject to the approval of the Responsible Engineer prior to the award of the contract. The proposed method of measurement shall be briefly listed on the Proposal Bid Sheet (item 1) to be evaluated in detail with price structure of each proposal after submittal.

d Specification I

CE-165'age 3

Revision 0 9/25/92

The past method of data collection used was through the use ofjig transits and optical micrometers to read the displacement scales mounted to the exterior wall of the Containment Building.

Three (3) equipment set-up stations shall be utilized, one (1) at each azimuth. A fullset-up of equipment is required at each azimuth; however, only two (2) stations need be manned continuously during the I.L.R.T. At azimuths 40'42'nd 260'00'he measuring equipment will be set up at the floor elevation of approximately 253'6", with the backsite placed on the ring beam foundation located at elevation 231'8".

Atazimuth 166'7'he measuring equipment willbe set up at floorelevation 271'0" with the backsite placed at elevation 253'6". The accuracy of each reading willbe required to be within J 0.005 inches.

~'.2 Deliverables At the completion of the radial displacement measurement work, supply the following items:

7.0 A.

Certification and calibration paperwork for personnel and equipment used to perform the measurements.

B.

A hard copy of the raw measurement data showing angle and distance information.

C.

A tabulated presentation of the measurements taken at each location showing displacement versus Containment Building pressure.

D.

A graphical presentation of the measurements taken at each location showing displacement versus Containment Building pressure.

E, The originals made of any calculations performed or drawings made.

F.

The original documentation of any computer printout or hand printed'ocumentation compiled for this work.

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'wner will remove penetration fire barriers necessary to establish straight line-of-sight viewing as detailed on RG&E Drawing 133013-2598.

The following areas are expected to require fire barrier removal.

A.

Auxiliary Building Operating Floor Level 271'0", penetration number A-57-P.

B.

AuxiliaryBuilding Intermediate Floor Level 253'0", penetration number A-139-P.

C.

Intermediate Building (West) Basement Floor Level 253'6", penetration number I-16-P.

D.

Intermediate Building (West) Exhaust Fan Floor Level 293'0", penetration number I-57-P.

E.

Intermediate Building (North) Basement Floor Level 253'8", penetration number I-90H-P.

Specification CE-165 l

Page 4 Revision 0 9/25/92 I

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7.3 Owner will relocate or remove any obstruction that interferes with line of sight viewing.

Owner willprovide lighting and other electrical requirements.

7.4 7.5 8.0 0

8.1 Owner willdetermine and provide necessary decontamination of work areas.

Owner willprovide Radiation Protection personnel, equipment and dosimetry for the work.

W~KK HH LH Outage schedules are subject to change based on operating conditions.

Contractors will be notified of any such schedule changes.

A.

Tentative 1993 Refueling Outage period willrun from March 19, 1993 to May 8, 1993.

B.

C.

Work scope herein will be performed during the I.L.R.T scheduled to run from April23 to April 28, 1993 on an around the clock schedule.

Contractor willbe notified of the work start date 60 days prior to start of outage.

8.4 The Work shall be scheduled on the basis of two shifts per day of twelve (12) hours per shift, seven (7) days per week, until such times as the work is complete.

Contractor shall adequately man and equip the job and work such hours and days as may be necessary to meet the work schedule.

The Owner willwork with the successful Bidder to schedule the work in coordination with the performance of the I.L.R.T.

Personnel proposed by the Contractor shall be involved in manning the Work throughout the duration of the Contract.

When necessary due to absence by regularly assigned personnel, other personnel shall be brought in to perform the necessary activities, to assure work schedules or due dates are not jeopardized.

Such substitutions ofpersonnel shall not be a basis for a change to costs.

Supervisory personnel changes shall be approved by the Owner in writing prior to being made.

9.0 Oi 91 E

B NDITI Final report shall be submitted to Owner within forty-five (45) days of measurement completion. Alldata measurements become the sole property of Owner.

SpeciTication CE-165 Page 5 Revision 0 9/25/92

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9.2 10.0 Site Access and Training Cost Reimbursement:

Certain costs associated with Site Access and Training activities required by the Owner willbe reimbursed to the Contractor (and subcontractors) in accordance with the terms of the contract documents included with this request for services.

I E D

PERMIT 11.0 The Bidder shall comply with all Federal, State of New York, and Local Codes, Ordinances, Laws and Regulations relating to execution of the Work.

I RP ETAT F

H LD ME 12.0 If a Bidder is in doubt as to the true meaning or intent of any part of the technical documents, the Bidder willsubmit a written request for interpretation.

The interpretation willbe made by Addenda only, and issued to all Bidders on record.

Bidders willstrictly adhere to the Owner's written interpretation of all documents.

The Owner will not be responsible for any other explanations or interpretations.

BID ER'EETIN A

EXAMI F

There is no formal bidder's meeting scheduled.

However, it is recommended that each Bidder visit the site to gain a good understanding of working conditions and constraints on the Ginna site that will impact the performance of the required scope of,work.

Those visits should be arranged with Mr. John J. Ferraro, Responsible Engineer, RG&E Nuclear Engineering Services at (716) 724-8115.

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id SpeciTication

~ CE-165 Page 6.

Revision 0 9/25/92

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'9 9~PALP RM P

P BID HEE ATTACHMENT¹1 TO CE-165 Containment Building Radial Displacement Measurement Services for the R. E. Ginna Nuclear Power Plant EWR ¹5181

~DEDATE 9 Id I, D t 9 III,1992 Materials Management Department.

Rochester Gas and Electric Corporation 49 East Avenue Rochester, New York 14649 1.

Proposed measurement method:

2.

The cost of providing all services required for the manpower, equipment, data accumulation and final report as described in Specification CE-165.

Total Lump Sum Bid It X

~HR X

~HR X 3.

The total lump sum bid shall be broken down as follows:

Ay a.

Personnel 1.

Straight Time Rate 2,

Overtime Rate 3.

Premium Time Rate,

~H

~H

= 2

~HR

=9 b.

Equipment 4~

Exceptions and specific deviations taken from the Specification CE-165, as listed:

5.

For scope additions or conditions beyond Contractor's control provide the all inclusive daily rates for the total organization, services, and equipment as follows; Mobilization Charge Demobilization Charge

~

6.

The submittal of a bid for this project hereby certifies the bidder and each person on the bidder's behalf, to the conditions of the contract documents.

Witnessed By:

Bidder:

,0 JF<270 ig By:

ITS:

Date:

ATTACHMENT02 TO CE-165 NTAINME 8 ILDIN RADIALDI PLA EME MEA EME ERV RAWI I

EX HE RG&E 33013-2132 Plant Arrangement - Reactor Containment Building Cross-Section 33013-2598 5181-SK-1 I.L.R.T.

Structural Instruments Replacement of Displacement, Plan and Section 3.

1993 I.L.R.T. Ideal Schedule I

JJF)271'

RG+E DRAWING¹5181-SK-1 IDEALILRTSCHEDULE 1993 ILRT 35 30

~ 25 K

g 20 K

I-z 15 z

r-10 z0O 0

0 10 20 30 DURATION(hours) 40 50 60 CE-165

4'

,~

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROILED COPY NUMBER PROCEDURE NO.

RSSP-6-5 REV.

NO.

4 EGRAT D LEAK CONTAINMENT STRUCTURA NSPECTION TECHNICA R

EW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

THIS PR CONTAINS 8

PAGES r%'

GINNASTATIOg START:

t DATE TIME CQMPI ETPD DATE

0

RSSP-6-5:1 1 ~ 0

~~ST:

This procedure provides the necessary instructions to perform a general visual structural inspection of the accessible interior and exterior surfaces of the containment structure and its components prior to, during and after the performance-of tests intended to measure the primary reactor containmihnt system overall Integrated Leakage Rate (Type A-I.L.R.T.).

This inspection is designed to uncover any evidence of structural deterioration which may affect either the containment structural integrity or leak tightness.

2 '

So 2 '

2 ~ 1.1 2 ~ 1.2 2 ~ 1 ~ 3 Scope A visual inspection of all accessible interior and exterior surfaces of the containment structure prior to the performance of any Type A containment structure Integrated Leak Rate Test (I.L.R.T.).

A visual inspection of all accessible exterior surfaces of the containment structure after attaining the maximum test pressure of any Type A-I.L.R.T.

A visual inspection of all accessible interior and exterior surfaces of the containment structure more than twenty-four (24) hours after fulldepressurization from any Type A-I.L.R.T. to allow for total stress relaxation of the structure'.

2 ~ 1.4 The visual examination of any accessible concrete surface on the containment structure, including

> ""',coated

areas, shall include visual examination for

'tress, deterioration, or excessive cracking which

',.be indicative of damage or degradation, such as e

examples defined in ACI 201.1R-68, "Guide For Making A Condition Survey of Concrete In Service".

RSSP-6.5:2, 2 ~ 1.5 The visual examinations required by this procedure are -the'responsibility of the Structural Engineering

'roup"and shall be performed by or under the direction of a registered Professional Engineer experienced in evaluating the in-service condition of structural concrete.

2.2 2 ~ 2 ~ 1 2 '

2 ' '

2'.2 2 '

Exempt Items The following items are exempt from this visual examination:

portions of the concrete surface that are covered by

.the containment

liner, foundation

material, backfill or other adjacent structures, components and parts.

Acceptance Criteria Prior to commencement of any Type A-I.L.R.T.,

any, evidence of deterioration or degradation found during the pre-test visual inspection shall be reviewed and evaluated by Engineering.

Pressurization for the I.L.R.T. shall not commence until a full evaluation has been performed by Engineering and any corrective action required is taken.

Prior to the commencement of any Type A-I.L.R.T., any pattern of cracking that exceeds one-one hundredth (0.01) of an inch in width and six (6) inches in length shall be mapped.

Inspection and mapping of each such area shall be performed before pressuriza-tion, at each pressure increment specified in RSSP-6.0, and after the test.

Each area mapped should include at least, forty (40) square feet.

At the conclusion of any Type A-I.L.R.T., no visible signs of permanent damage to either the containment structure or the steel liner shall be evident.

Evidence of spalling, laminations or voids behind the liner are pertinent considerations.

Special care shall be exercised to detect any evidence of localized distress: if areas of localized distress are detected, a 'full evaluation shall be performed by Engineering

. determine if any corrective action is required fore this procedure is signed off.

Alg 3.0 3 ~ 1 Procedure No.

RSSP-6. 0, Containment Integrated Leakage Rate Test.

RSSP-6.5:3 3 '

3 '

10CFR50, Appendix J, "Leakage Tests For Containments of Light-Water-Cooled Nuclear Power Plants".

ASME Section III, Div. 2, Article CC-6000 and Article IWL-2420.

3.4 3.5 SEP Topic III-7.A, In-Service Inspection Xncluding Pre-Stressed Concrete Containments with Either Grouted or Ungrouted Tendons.

ACI 201.1R-68, Guide for Making a Condition Survey of Concrete In Service.

3.6 ANSI/ANS-56.8-1987, Containment System Leakage Testing Requirements.

4 0

F 1 XNITXALCONDXTXO S:

Plant is in cold shutdown status.

4 ~ 2 M-102 Inspection

& Maintenance of Containment Liner Xnsulation has been performed by the Ginna Plant Maintenance Group and is completely signed off..

4 '

An SWP has been obtained for inspections which require entry to locked high radiation areas.

4 ~ 4 4.5 Notify Health Physics prior to performing inspection of Tendon Anchor Heads to establish radiation protec-tion requirements.

Inspection substeps need not be done in sequence, except where specifically stated.

4 '

Notify ILRT Test Coordinator at start of inspection.

5 '

5 '

CAUTXO S:

serve company safety rules and Ginna Station Health ihysics rules while performing inspections.

g

0

RSSP-6.5:4 6.0 0

F 1 6 ~ 1.1 XZXEKZR:

Perform a visual inspection of the exterior surface of the Containment structure prior to pressurization for any Type A-I.L.R.T. at the following locations.

The sequence of inspection can be performed in any order:

F 1.1.1 Access the walkway around the Containment Building tendon anchor heads from the west stairwell of the Turbine Building and the roof of the adjacent Inter-mediate Building.

Inspect the concrete around all of the tendon anchor head assemblies for" signs'f deterioration or cracking described by Section 2.1'.4.

6. 1. 1.2 I

Access the areas around the equipment hatch from grade elevation on the east

side, adjacent to the main transformers.

Inspect the concrete around the equipment hatch for signs of deterioration described in Section 2.1.4.

6 1. 1.3 6.1.1.4 Access all floor levels of the north section of the Intermediate Building, including the walkway adjacent to the "B" loop main steam line.

Inspect the concrete at each level for signs of deterioration described by Section 2.1.4 at the following elevations:

Intermediate Building South (Controlled Area) locations:

a ~b.

co d 0 e.f.

Sub-basement 9 237'-0",& 238'-6" Basement 9 253'-6" Platform 9 267'n Floor 9 271'-0" (HP depk area)

Floor 9 293'-0" rooftop 9 318'-0" (IB low roof) 6.1 ~ 1 ~ 5 Intermediate

." 41ocations:

t V

E Co doe.f.

Basement 9 253'-6" Platform 9 267'-3" Floor 9 267'-3n Floor 9 298'-4" Floor 9 315'-4" Rooftop 9 336'-6" (IB High Roof).

Building North (non-controlled area)

I 0

RSSP-6.5:5 6.1.1.6 Basement floor 9 235'-8~I Intermediate floor 9 253'-0" Operating floor 9 271'-0" Platform floox 9 311'-6" Access all iloox levels of.the Auxiliary Building.

Inspect the concrete for signs of deterioration at each of the following elevations:

4

~ ~<<$:.-,a e b ~

Cod.

6.2 6.2

~ 1 6.2

~ 1 ~ 1 XHXEBXQB-'erform a visual inspection of the interior surface of the Containment structure prior to pressurization for any Type A-I.L.R.T. at the following"locations.

The sequence of inspection can be performed in any order:

I Access all floor and platform levels of interior of the Containment Building.

Inspect the liner for localized distress or indications of concrete deterior-ation behind the

linex, as described in Section 2.3.3, at the following elevations:

a.

Basement floor level 9 235'-8" b.

Intermediate floor level 253'-3" c.

Operating floor level 278'-4"

& 274'6" d.

Air filter platform level 300'-4~

e.

Containment Building crane platform level 320'-6" 6 ' '

Notifythe ILRT Test, Coordinator, immediately following completion of sections 6.1 and 6.2, that Containment pressurization may be started as directed by RSSP-6.0.

6 '

E 3

o 60 s

6 ~ 3 ~ 1

6. 3. 1 ~ 1~'

~(

Perform a visual inspection, in any sequence, of the exterior surface of the containment structure after stabil,ization at full pressure fox any Type A-I.L.R.T.

-'jV~fy that the inspection has been completed on 4s shown below:

.the walkway around the Containment Building dii","anchor heads from the west stairwell of the "ine'uilding and the roof of the adjacent Inter-mediate Building.

Inspect the concrete around all of the tendon anchor head assemblies for signs of deterioration or cracking described by Section 2.1.4.

0

RSSP-6 5:6

~ <<II<<

A 6 ~ 3 ~ 1.2 Access the areas around the equipment hatch from grade elevation on the east

side, adjacent to the main transformers.

Inspect the concrete around the

~,,equipment hatch for signs of deterioration described in Section 2;1.4.

6'.1.3 6.3.1.4 6.3. 1.5 Access all floor levels of the North section of the Intermediate Building, including the walkway adjacent to the "B" loop Main Steam line.

Inspect the concrete at each level for signs of deterioration described by Section 2.1.4 at the following elevations:

Intermediate Building (Controlled Side) locations:

a.

Sub-basement 9 237'-0" 6 238'-6" b.

Basement 9 253'-6" c.

Platform 9 267'-3" d.

Floor 9 271'-0" '(HP desk area) e.

Floor 9 293'-0" f.

Rooftop 9 318'-0" (IB low roof)

Intermediate Building (clean side) locations:

a ~b.

C ~d.e.f.

Basement 9 253'-6" Platform 9 267'-3",

Floor 9 267'-3" Floor 9 298'-4" Floor 9 315'-4" Rooftop 9 336'-6II (IB high roof) 6 ~ 3.1.6 Access all floor levels of the Auxiliary Building.

Inspect the concrete for signs of deterioration at each of the following elevations:

a ~b.

Co d 0 Basement floor 9 235'-8" Intermediate floor 0 253'-0" Operating floor 9 271'-0" Platform floor 9 311'-6" e

6.3.2 Notifythe ILRT Test Coordinator, immediately following

.completion of section 6.3, that Containment depressuri-giOg::may be started as directed by RSSP-6.0.

iPh'I'i 6.4 SS r,

6;4.1

'~.'. er88rm a visual inspection, in any sequence, of both the exterior and interior surfaces of the Containment structure at least twenty-four (24) hours after depressurization from any Type A-I.L.R.T. and verify that the inspection has been completed on the* lines shown below:

RSSP-6 ':7 6-4'.1 Access tile walkway around the Containment Building tendon anchor heads from the west stairwell of the

->,,'.cpu'bine Building and the roof of the ad)acent Inter-

~aediate Building.

Inspect, the concrete around all of

'-., the tendon anchor head assemblies for signs of deterioration or cracking described by Section 2.1.4.

6 ~ 4 ~ 1.2 Access the areas around the equipment hatch from grade elevation on the east

side, adjacent to the main transformers; Inspect the concrete around the equipment hatch for signs of deterioration described in Section 2;1.4.

6 ' '.3 6.4.1.4 Access all floor levels of the north section of the Intermediate Building, including the walkway ad)acent to the "B" loop main steam line.

Inspect the concrete at each level for signs of deterioration described by Section 2.1.4 at the following elevations:

Intermediate Building South (controlled area) loca-tions:

a 0 b.

Ce dee.f.

Sub-basement 9 237'-0"

& 238'-6"

Basement, 9 253'-6" Platform 9 267'-3" Floor 6 271'-0" (HP desk area)

Floor 9 293'-0" Rooftop 0 318'-0" (IB low roof) 6.4 '.5 Intermediate Building North (non-controlled area) locations:

6.4.1a6';

a.

Basement 9 253'-6" b.

Platform I 267'-3" c.

Floor 9 267'-3" d.

Floor 6 298'-4" e.

Floor 6 315'-4" f.

Rooftop 9 336'-6~

(IB high roof) fags'fesll floor levels of the Auxiliary Building.

e concrete for signs of deterioration at

'6fi~4he following elevations:

.>'>.58sEment floor 9 235'-8"

'Mfttermediate floor 9 253'-0" c.

Operating floor 6 271'-0" d.

Platform floor 0 311'-6"

~8 RSSP-6.5:8

'C C

6.4.1 '

. Perform a visual inspection of the interior surface

.,,,of the Containment structure after depressurization.

<<;,;.;,i~+"." rom any Type A>>I.L.R.T. in the following manner:

I I 6.4.1.8,j ccess all floor and platform levels of interior of

~e Containment Building.

Inspect the liner for

,;.=..Kocalized distress or indications of concrete deteri.or-

"ation behind the

liner, as described in Section 2.3.3, at the following elevations:

a ~

b.

co d 0 e ~

Basement floor level 0 235'-8" Intermediate. floor level 253'-3" Operating floor level 278'-4" 274'-6" Air filter platform level 300'-4" Containment Building crane platform level 320'-6" 6.5 Upon the completion of this procedure for any Type A-I.L.R.T,

this procedure and the data 'btained through its implementation shall be reviewed and signed off by a

representative of the Structural Engineering Group on the.line below:

~

~

}s~}'~

'L

}

gA.

'I.;:s

. ~

STRUCTURAL ENGINEERING:

(

)

HEAD CONTROL OPERATOR:

SHIFT SUPERVISOR:

RESULTS

& TEST REVIEW:

DATE:

~

~

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO.

SSP-6.0 REV.

NO. ~9 CON A ENT N EGRAT D LEAKAGE RAT TECHNICAL REV EW PORC REVIEW DATE P

NT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

THIS PROCEDURE CONTAINS 40 PAGES 6INNASTATION START:

DATE TIfviE COViPL TED:

DATE T!ME:

RSSP-6.0'1 G

T S

1.0 PURPOSE

To provide steps for conducting the Type

<<A<<

Containment Integrated Leakage Rate Test (ILRT) and Verification Test.

2.0 TEST RE UIRElGBFZS:

2 ~ 1 To verify that leakage from Containment does not exceed the allowable leakage rate for reduced pressure testing governed by the following relationship:

(

Lt = La (Pt/Pa) ~

Lt = (.2)

(35/60)

~

=.1528 wt. 4/day THEREFORE

.75 Lt = (.75)

(.1528)

=.1146 wt. 4/day Where:

Lt =

maximum allowable leakage rate at Pt (wt. 4/day)

La

=

maximum allowable leakage rate at Pa (0.2 wt. 4/day)

Pt = Reduced test pressure (35 psig)

Pa

= Accident Pressure (60 psig)

V

= Containment Free Volume (1.0 x 106 ft.

)

2.2 2 ~ 3 The allowable operational leakage rate (Lt) which must be met prior to resumption of power operation following a test is not to exceed 0.75 Lt.

The measured leakage rate (Ltm) is not to exceed

.75 Lt at the upper 95%

confidence level using Mass Point or Total Time Analyses methods.

Instrumentation used to determine leak rate should remain operable during the entire test.

As a minimum, one Containment pressure instrument, sixteen Contain-ment temperature

RTDs, and three dewpoint sensors shall be operable; otherwise, the test may be. invalid.

If a spurious reading is obtained and it appears not to be attributable to a sensor malfunction, the data rejection criteria of ANS 56.8-1987, Appendix D may be applied for the purpose of rejecting that datapoint.

0

0 RSSP-6.0:2 3.0 csee 3 ~ 1 3.2 3 ~ 3 3.4 3.5 3.6 3 '

3.8 3.9 R.E. Ginna Nuclear Power Station, "Type "A" Reactor Contaihment Building Periodic Retest Results".

Technical Specifications, Section 4.4;1.

10 CFR 50, Appendix Z..

ANSI N45 ~ 4-1972.

ANSI/ANS 56.8-1987.

BN-TOP-1, Rev.

1 1972.

Reg.

Guide 1.18, Rev.

1, 12/28/72, "Structural Accep-tance Test for Concrete Primary Reactor Containments".

I RSSP-6.5, ILRT Containment Structural Inspection.

NSL-OOOO-DA042, Design Analysis Ginna Station Contain-ment Isolation Valve Listing.

4.0 IN TIAL CONDITIONS:

4.1 4.2 SIPE Implementation Control Form has been completed per A-52.15.

Preparational steps within this procedure need not be performed in sequence, but as directed by the test coordinator.

4.3.

4.4 An events log willbe maintained throughout the testing interval, from start of initial pressurization of the Reactor Containment Building to the conclusion of final depressurization of the building.

Plant is in Cold Shutdown condition.

4.5 Residual Heat Removal System is in service as required, to maintain proper Reactor Coolant System Temperature.

EMOTE:

PZR level will~dec ease during pressurization and make-up may be required,.

PZR level will increase during depressurization.

4.6 Notify Operations to initiate Attachment E,

RCS Level Control, steps 1.1 to 2.7, to ensure the Pressurizer'as an indicated level of < 50% and will be vented to the Containment atmosphere.

II P

0 RSSP-6.0:3 4 '

4.8 The required ILRT panel instrumentation has been calibrated within 6 months prior to'erforming test.

Records of calibration will be maintained and will be traceable to NBS (See Attachment A-Instrument Cali-bration Data).

To assess any possible external effects upon test

results, the following data will be recorded and/or logged at intervals of less than or equal to, 1 hour:

4.8. 1 4.8.2 4.8.3 Barometric pressure.

Temperature.

Weather Conditions, windy, etc.

e.g.

cloudy,

rainy, clear, 4.9 Lead test personnel are qualified in accordance with A-1102 and have had a

Pre-test briefing on test requirements.

4'0 4.11 Notify Shift Supervisor at start of test.

Notify Head Control Operator at start of test.

4.12 4.13 Notify Q.C. Dept at start of test.

Health Physics Work Permits have been issued to facilitate inspection of all affected areas for duration of the test.

4.13 '

Notify HP that a Constant Air Monitor (CAM) will be needed at the ILRT panel inside door 37, prior to the start of Containment pressurization.

4. 14 4'4 '

Ensure the following procedures have been completed to the point where pressurization may commence:

RSSP-6.1 ILRT Valving Alignment.

4. 14. 2 RSSP-6.2 Pressurization Monitoring of Penetrations During Containment ILRT.

4.14.3 RSSP-6.3 Air Supply for ILRT.

4'4 '

4 '4.5 RSSP-6.-4 ILRT Instrument Integrity Check.

RSSP-6.0:4 RSSP-6.5 ILRT Containment Structural Inspection.

(Sections 6.1 and 6.2 complete)

4. 14. 6 RSSP-6.6 Hydro Test of CV Air Test After Cooler (Optional, may be marked N/A if not performed).

4.14 '

4.14.8 RSSP-6.7 ILRT Instrumentation Preparation.

RSSP-6.8 ILRT RTD Temperature Survey.

(Optional, may be marked N/A if not performed)..

4.14.9 RSSP-6.9 ILRT Dewcell Survey.

marked N/A if not performed).

(Optional, may be 4.14.10 Installation of "A" and "B" S/G Handhole covers, GMS-43-11.

4 '4.11

4. 14. 12 Installation of "A"

and "B"

S/G Secondary Manway

Covers, GMS-43-12.

Installation of 3" Diameter Inspection Port Cover Number 4 Wedge Area, GMS-43-20.

4. 14. 13 Installation of 3" Diameter Inspection Port Cover Number 6 Wedge Area, GMS-43-21.

4. 14. 14 4.14.15 Installation/Removal of Purge Supply and Exhaust

Flanges, M-101.

Containment Isolation Valve Leak Rate Testing Purge Supply and Purge Exhaust PTT-23.35.1 and PTT-23.36.1.

4. 14

~ 16

4. 15 4.15.1 PT-22.1

& 22.2 to ensure Personnel

& Equipment Hatch Seal Integrity.

Obtain the following pre-test levels and record on Attachment D:

CONTAINMENT SUMP A LEVEL MCB indicators LI 2039 LI 2044

RSSP-6 0:5 4.15.2 CONTAINMENT SUMP B LEVEL Dip stick method 4.15.3 PRESSURIZER COLD CALIBRATION LEVEL MCB indicator LI 433 4.15.4 REACTOR COOLANT DRAIN TANK LEVEL - WDP LI-1003

4. 15.5 PRESSURIZER RELIEF TANK LEVEL MCB indicator.

LI-442 4.16 Ginna Station Test Tag Control Program, A-1103, shall be utilized as required for test tags prepared under Attachment "C".

4'7 I

Notify Fire Protection that fire system Z-16 must be disconnected for entire duration of ILRT.

4. 18 Notify Structural Engineering Dept. that initial pre-pressurization radial displacement measurements may be taken.

5.0 5.1 5 '

To avoid the possibility of having to abort the test, resulting from valving alignment other than that required for test

period, all. daily anticipated maintenance work on Primary System valving and piping must be* discussed and cleared with Results and Test Supervision.

In addition, test personnel should be instructed not to perform valving alignments or tighten fittings or packing without clearance from Results and Test Superviqion.

This is especially important during any leak detection operations.

Failure to observe this may result in failed test even though leakage rate is acceptable.

During the period between the initiation of the Containment inspection and performance of the Type A

, Test, no repairs or adjustments shall be made so that the Containment can be tested in as close to "as is" condition as practical.

However, if during the Type A test repairs and/or adjustments are necessary, a

new Type A test shall be initiated and any such associated corrective actions taken, will be included in the final report submitted to the NRC.

RSSP-6.0:6 5.3 5.4 5.4 '

Necessary steps will be taken by all departments to afford protection for equipment inside Containment, which could be subject to damage as a result of test pressure.

(e.g. - fire detection

systems, unvented

tanks, pressure sensitive devices.)

In the unlikely event an inspection team is required to enter Containment (at approximately 14 psig level),

the Containment, air activity will be monitored by the Health Physics Department and the following precautions observed:

(Refer to procedure A-1.6.4 "Requirements For Safe Work In Confined Spaces" ).

At least 6

minutes will be utilized for pressure equalization as personnel are passing through the personnel hatch.

Personnel are not to be subjected to the 14 psig level for a time period in excess of two hours.

5.4.2 5.4.2.1 5.4.2.2 5.5 5.6 When exiting Containment, hatch depressurization should not exceed the rates specified below.

Use a portable pressure indicator for monitoring.

Stage 1.

Pressure reduction from 14

psig, at an essentially uniform rate

< 5 psig/minute, to 4 psig.

Stage 2.

Pressure reduction from.

4

psig, at an essentially uniform rate

< 1 psig/minute to 0 psig.

Test control tags will be placed on concerned valves and equipment to ensure that alignment conditions are maintained throughout the testing. interval.

The isolation valve/valves of any system (excluding RHR system) remaining in service during the testing interval shall be subjected to a

local Class C

leakage check upon completion of the ILRT.

Any existing local leakage shqll be added to the results of'LRT.

5.7 5.8 To assure no infiltration of air into the Containment building during the test, the air supply header shall be vented to atmosphere after attaining desired pressure.

Wear ear protection when working at compressors or depressurizing Containment.

~ '

RSSP-6.0:7 6.0 6.1 6.1.1 Ensure the following fans are secured:

, Containment Auxiliary Charcoal Filter Fans.

A B

6. 1.2 6.1.3 Reactor Compartment Cooling Fans.

Control Rod Shroud Fans.

A B

A B

6.1.4 Reactor Cavity Supply and Exhaust Fans.

Supply Exhaust 6.1.5 Mini-Purge Supply Fan.

6.1.6 Containment Recirculation Fans.

A B

C D

6 '

Depressurize the Safety Injection Accumulators and the Overpressurization Accumulators to Containment atmosphere in accordance with S-16 series, if not already done.

6.2.1 Remove blind flange at SI Accumulator "A" manual vent and open manual vent valve 886A.

Leave open for duration of test.

6'.2 Remove blind flange at, SI Accumulator "B" manual vent and open manual vent valve 886B.

Leave open for duration of test.

6.3, 6 ~ 3 ~ 1 Ensure that the blind flanges are removed from the following lines inside containment:

In"egrated Leakage Rate Test Supply (Penet.

317) 6.3.2 Integrated Leakage Rate Test Exhaust (Penet.

313)

RSSP-6.0:8 6.4 Ensure that the flanges are removed from

~ot Integrated Leakage Rate Test Exhaust Lines located on the Int. Bldg. roof adjacent to the Containment dome.

6.5 6.6 6;6 ~ 1 6.6.2 6.6.3 6.6.4 6.6.5 6.6.6 Verify with Operations that Attachment E,

steps 1.i to 2.7, has been completed.

To avoid unwanted safeguard signals as Containment pressure is being increased, pull fuses on individual power. supplies in Relay Room as follows:

PQ 945 fuses pulled.'Q 946 fuses pulled.

PQ 947 fuses pulled.

PQ 948 fuses pulled.

PQ 949 fuses pulled.

PQ 9$ 0 fuses pulled.

~NOT Any associated difficulties and/or discrepan-cies identified in'he next step must be resolved before proceeding with Containment pressurization.

6.7 Verify with Structural Engineering personnel assigned to the Containment inspection

team, (both interior and exterior) that these inspections have been completed as per Initial Condition 4.14.5 inclusive.

6.8 At MCB, initiate Containment Isolation and Containment Ventilation Isolation by pressing either one of the "MANUAL CONTAINMENT ISOLATION" pushbutton switches.

6.8.1 Place Test Tags on "CONTAINMENT ISOLATION RESET" and "CONTAINMENT VENT ISOLATION RESET" switches to ensure isolation valves cannot be re-opened until required by procedure.

QQQ:

RSSP-6.0:9 Although AOV 427 is not a

Containment Isolation valve, it will go Closed on the Containment Isolation Signal and re-open upon loss of Instrument Air.

6.9 Verify the following automatic Containment Isolation valves are

<<CLOSED<<

using normal indicators and/or status light (bright light, closed) indicators.

NOTE:

Notify the ILRT Test Coordinator of any valve not found in the "CLOSED" position prior to initiating corrective action.

6.9.1 6.9 '

6.9 '

6 ' '

6.9 '

6.9 '

6'.7 6 '

6.9 '

6.9 '0 6 ~ 9 ~ 11 6.9 '2 6.9 '3 6 ' '4 SOV 921, H2 Mon.

A Inlet SOV 922, H2 Mon.

A Outlet AOV 539, PRT To Gas Analyzer AOV 1789, RCDT To Gas Analyzer AOV 1786, RCDT To Vent Hdr.

AOV 1787, RCDT To Vent Hdr.

AOV 1721, RCDT Outlet AOV 1003A, RCDT Pmp.

A Suet.

AOV 1 0 03B g RCDT Pmp B Suet

~

AOV 1597, R10A/R11/R12 Suction AOV 1598, R10A/R11/R12 Discharge AOV 1599, R10A/Rll/R12 Discharge MOV 813, CCW To Rx Supp. Clrs.

MOV 814, CCW From Rx Supp. Clrs.

6.9.15 AOV 1723, Sump A Disch.

6.9.16 6.9 17 6.9.18 6.9.19 6.9.20 AOV 1728, Sump A Disch.

SOV 923, H2 Mon.

B Inlet SOV 924, H2 Mon.

B Outlet AOV 371, Ltdn. Line Isol.

MOV 313, RCP Seal Return

k 4

RSSP-6 ':10 6 ' '1 6.9 '2 6 ' '3 6.9.24 6.9.25 6.9.26 6.9.27 6.9.28 6.9.29 6.9.30 6.9.31 6.9.32 6.9.33 6.9.34 6.9.35 6 ' '6 6.9.37 6.9.38 6 '.39 6.9.40 6.9.41 6.9.42 6.9.43 6.9 '4 6'.45 6.9.46 AOV 951, Pzr.

Stm.

Samp. In AOV 953, Pzr. Liq. Samp. In AOV. 955, B Hot Leg Samp. In AOV 959, RHR Sample AOV 966A, Pzr.

Stm.

Samp.

Out AOV 966B, Pzr. Liq. Samp.

Out AOV 966C, Hot Leg Samp.

Out SOV 1A, H2 Recombiner SOV 2A, H2 Recombiner SOV 3A, H2 Recombiner SOV 5A, H2 Recombiner AOV 8418, Cnmt.

DI Water AOV 7971, Mini Purge Exh.

AOV 7970, Mini Purge Exh.

AOV 7445, Cnmt. Lk. Test Disch.

AOV 7478, Cnmt. Mini Purge Supply.

AOV 5879.,

Cnmt.

Purge Exh.

AOV 5869, Cnmt.

Purge Supply AOV 846, Accum N2 Supply MOV 7443, Cnmt. Lk. Test Sup.

AOV 5392, Cnmt. Instr. Air MOV 7444, Cnmt. Lk. Test Disch.

SOV 1B, H2 Recombiner SOV 2B, H2 Recombiner SOV 3B, H2 Recombiner SOV SB,,H2 Recombiner

P 1

n

RSSP-6 '

11

'6.9.47 6.9.48 6.9 '9 6.9.50 6'.51 6.9.52 6.9.53 AOV,9227, Cnmt. Fire Hose Supply AOV 5738, S/G B Bldn. Isol.

AOV 5737, S/G A Bldn. Isol.

AOV 508, RMW To Cnmt. Vess.

AOV 5735, S/G A Sample AOV 5736, S/G B Sample SV 1600A, RCDT To GA Sample Isol. Vlv.

(Verify on C.I. Reset Panel)

~NO The following steps may be performed out of sequence at the discretion of the ILRT Test Coordinator.

6.10 6.10.1 Prior to start of pressurization of Containment perform the following:

Verify the following Containment Isolation valves closed at the field location by observation of mechanical indicators:

6'0 ' '

6.10 ' '

6.10.1.3 6.10.1.4 6'0.1 '

6 '0.1.6 6'0'.7 6.10 '

6.10 '.9 INT. BLDG CLEAN SIDE TDAFP AREA MOV 7443, Cnmt. Lk. Test Sup.

(P-317)

AOV 5392, Cnmt. Instr. Air (P-310).

MOV 7444, Cnmt. Lk. Test Disch.

(P-313)

AOV 7445, Cnmt. Lk. Test Disch.

(P-309)

AOV 8418, Cnmt.

DI Water (P-324)

AOV 9227, Cnmt. Fire Hose Supply (P-307)

AOV 5738, S/G B Bldn. Isol.

(P-321)

AOV 5737, S/G A Bldn. Isol.

(P-322)

AOV 1597, R10A/R11/R12 Suction (P-305) 6.10.1.10 AOV 1598, R10A/R11/R12 Discharge (P-305),

6.10.1.11 AOv 1599, R10A/R11/R12 Discharge (P-305)

'6.10.1.12 SOV 10205S1, "A" H2 Recombiner (P-304)

h 0

e RSSP-6.0:12

6. 10 1. 13 SOV 10209S1, "A" H2 Recombiner (P-304)

I N

BLD. - CONT 0 LED SAMPL HOOD 6.10.1.14 AOV 5735, S/G A Sample (P-206) 6.10.1.15 AOV 5736, S/G B Sample (P-207) 6.10.1.16 AOV 966A, Pzr.

Stm.

Samp.

Out (P-207) 6.10.1.17 AOV 966B, Pzr. Liq. Samp.

Out (P-206) 6.10.1.18 AOV 966C, Hot Leg Samp.

Out.(P-205) 6.10.1

~ 19 6.10 ' '0 6.10.1 '1 6'0 F 1.22

~ SOV 10214S1, H2 Recombiner 02 (P-210)

SOV 10214S1, H2 Recombiner 02 (P-210)

SOV 10215S, H2 Recombiner 02 (P-210)

SOV 10215S1, H2 Recombiner 02 (P-210) 6.10.1.22 SOV 10211S1, "B" H2 Recombiner (P-202) 6.10.1.23 SOV 10213S1, "B" H2 Recombiner (P-202)

AUX. BLDG.

6.10.1.24 MID FLOOR BY SFP H

AOV 508, RMW To Cnmt. Vess.

(P-121) 6.10.1.25 AOV 539, PRT To Gas Analyzer (P-120) 6'0 F 1'26 6.10 1.27 6.10.1.28 AOV 1789, RCDT To Gas Analyzer (P-123)

AOV 1786, RCDT To Vent Hdr.

(P-129)

AOV 1787, RCDT To Vent Hdr.

(P-129) 6.10.1.29 AOV 7971, Mini Purge Exh.

(P-132) 6.10.1.30 AOV 846, Accum N2 Supply (P-120)

AUX. BLDG.

ID FLOOR BY RWST 6.10.1.31 MOV 813, CCW To Rx Supp. Clrs.

(P-131)

RSSP-6 ':13 6.10.1.32 MOV 814,, CCW From Rx Supp. Clrs.

(P-130) 6.10.1 '3 6.10.1.34 AS N

WEST TA RS AOV 1723, Sump A Disch.

(P-107)

AOV 1728, Sump A Disch.

(P-107)

BASEME T BY RWST

6. 10. 1. 35 6.10.1.36 6.10.1.37 6.10.1.38 AOV 959, RHR Sample (P-111)

AOV 371, Ltdn. Line Isol.

(P-112)

MOV 313, RCP Seal Return (P-108)

AOV 1721, RCDT Outlet (P-143) 6.10.1.39 AOV 1003A, RCDT Pmp.

1A Suet.

(P-143) 6.10.1.40 AOV 1003B, RCDT Pmp.

1B Suet.

(P-143)

6. 10.2 Ensure that an ILRT Events Log Book is available for use throughout the test interval.

6. 10.3 Log initial pressure readings (penetration and manifold) for all concerned areas as listed on Data Sheets 1,

2 and 3.

6.10.4 Ensure that equipment is in place to monitor outside weather parameters.

6.10.5 Open states-blocks for MOV~s 7443 and 7444 to divorce Containment 'Isolation signal which will allow opening of these valves as

required, during pressuri-zation/depressurization period.

Location of states blocks in Relay Room Containment Isolation Relay

cabinets, is as listed below:

CI-A2 Cabinet (Rear)

TB-1 states block f61 MOV 7443 TB-1 states block f65 MOV 7444 Open Open

lt d

RSSP-6. 0: 14 TB-1 states block g61 MOV 7443 TB-1 states block'f65 MOV 7444 Open Open

~NOT Perform these alignment steps only after ILRT Test Coordinator has initiated the Containment Isolation signals.

6'0 '

6. 10 ~ 6. 1 Alignment of Instrument Air line:

Ensure "CLOSED" manual valve 5397 (outside C.V.).

Closed 6'0'.2 Establish vent to outside atmosphere, upstream of AOV 5392 by ensuring open test connection valves

5410, 5410A and 5410B.

Remove cap at 5410B.

Vented I

6.10.6.3 Depressurize Instrument Air header inside Containment and provide a vent to Containment, atmosphere, down-stream of check valve 5393 by placing control switch for 'AOV 834B to the Closed position. Vented 6 ~ 10. 7 6.10.7.1 6.10.7.2 6.10.8 After verifying that all personnel are out of Contain-

ment, shut off all inside lights and "LOCK CLOSED" the following access hatch outer doors.

Personnel Hatch Outer Door Equipment Hatch Outer Door Verify that Structural Engineering radial displacement measurements are complete.

6.11 6.11 '

CONTAINMENT PRESSURIZATIO D STABILIZATION PERIOD Inform the Shift Supervisor and Head Control Operator'hat Containment pressurization is about to begin and that an announcement regarding the start of the ILRT

~ over the Plant P.A. System is necessary.

6 ~ 11. 1. 1'stablish communications with Control Room to ensure personnel are available to maintain RCS Level Control as per steps 3.0 to 3.1.3 of Attachment E.

I RSSP-6 0:15, Start the ILRT air compressors as needed and initiate air flow to Containment by performing the following:

OPEN manual valve 7440 (Supply Isolation Downstream of PCV 7439).

At approximately 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> intervals after pressurization of Containment

begins, and until after obtaining the final data of the verification test

period, secure readings for all concerned Penetration manifold areas and record on Data Sheets, g1 and g2.

~NOT A flow rate of'200 SCFM will pressurize Containment at a rate approximately equal to 6.5 psig/hour.

Ad)ust air reducing valve PCV 154'68 to throttle open PCV 7439 and slowly admit air to Containment.

Start up additional compressor(s) only upon instructions from the ILRT Test Coordinator.

Ad)ust air flow to Containment to desired rate, staying within the capacity of the number of compressors running and a flow rate of approximately 7200 SCFM.

Upon reaching a Containment pressure of approximately 10 psig, the ILRT Test Coordinator shall dispatch an inspection team to conduct a comprehensive Containment external inspection, for the purpose of. identifying any leaks.

CAUTION:

In order to prevent.

overshoot of the Hold Point limits in the next. step, at a Contain-ment pressure of approximately 14

psig, begin removing air compressors as necessary and controlling air flow rate with PCV 7439.

Upon reaching a

Containment pressure of 15 psig,

+

.25 psig, the ILRT Test Coordinator shall maintain this pressure for approximately one hour to allow Structural Engineering to perform radial displacement measurements.

Structural Engineering has notified ILRT Test Coordinator that measurements are complete.

'I

\\

RSSP-6

~ 0: 16 11 '

3 Containment, pressurization may continue.

6.11.4.4 Re-establish air flow rate of approximately 7200 SCFM.

6. 11.5 Should a leak exist that may exceed La and the Test Coordinator, feels further investigation

~insi e Containment is warranted, stop pressurization and assemble the following inspection team consisting of the groups

listed,

'otherwise mark steps 6.11.5 through 6.11.8 inclusive N/A:

6.11.5.1 Instrument and Control 6.11.5.2

.Electrical 6.11.5.3 Pipefitters 6.11.5.4 Machinists 6.11.5.5 Operations 6.11.5.6 Results and Test 6.11.6 Request Health Physics Dept. to initiate Containment Entry procedures to allow assigned personnel to conduct an inspection.

The inspection groups will meet to discuss their responsibilities.

6.11 '

Upon completion of the Containment. inspection(s),

the inspection team(s) will meet briefly to discuss their findings.

The decision to continue with the test will be the responsibility of the ILRT Test Coordinator.

6 ~ 11 ~ 8 Start air flow to Containment and place in service the required number of compressors.

NOTE:

During the next step remove ILRT compressors from service consistent with the reduced air flow.

6. 11. 9 Upon reaching Containment pressure of approximately 33

psig, reduce rate of air flow into Containment to approach the desired ILRT test pressure (35 psig) gradually, thereby permitting temperature and pressure to stabilize without excessive overshoot.

II

PI I

0 II 0

RSSP-6.0:17 When Containment. pressure is a minimum of.3 psig above test pressure of 35 psig, as read on ILRT pressure gauge(s),

CLOSE Containment Air Test Inlet Isol. valve MOV-7443

'.11.10.1 6.11.10.2 CLOSE Air Dryer outlet valve 7435.

Depressurize air supply header via vent valve 7437 upstream of PCV 7439 and permit vent valve 7437 to remain '"OPEN".

6.11.10.3 Notify Control Room that pressurization is complete.

6. 11. 11 Verify that the air pressure inside Containment,

.based upon the ILRT pressure instruments, is above 35 psigo

6. 11. 12 Initiate logging of outside weather parameters on Meteorological Data Sheet g3 at. less than'r equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> intervals throughout the test.

6 ~ 11. 13 Notify Structural Engineering to perform radial displacement measurements.

6. 11. 14

6. 11. 14

~ 1 Permit the Containment Building contents to attain temperature stabilization in accordance with ANS 56.8, Section 5.3.1 or Bechtel Topical Report BN-TOP-1, Section 2.3 as indicated below.

Stabilization may take longer than four hours:

(Mark method not used N/A).

ANS 56.8:

The latest rate of change of the weighted average Containment air temperature, averaged over the last hour, does not deviate by more than 0.5 F/hr from the average rate of change of the weighted average Containment air temperature averaged over the last four hours.

6. 11. 14 2

BN-TOP:

Once the Containment is at test pressure the Ccotainment atmosphere shall be allowed to stabilize for approximately four hours.

The atmosphere is considered stabilized, when:

t

RSSP-6.0:18 (Indicate criteria used by initialing and mark other criteria N/A) 1.

The rate of change of average temperature is less than 1.0'F/hour averaged over the last two hours.

or 2.

The rate of change of temperature changes less than 0.5'F/hour/hour averaged over the last, two hours.

6. 12

6. 12. 1 TYPE nAn TEST PE IOD Upon reaching stabilized conditions, secure a line of initial pressure and temperature data.

Ensure that Containment Building pressure is 35 psig when starting this phase of test.

I NOTE:

Initial data (time zero) to be taken exactly on the hour, or as directed by the ILRT Test Coordinator.

6. 12.2 Notify Structural Engineering representative to perform applicable portions of RSSP-6.5.

~NOTE It may be desirable to acquire data at intervals more frequent than below.

This will be at the discretion of the ILRT Test Coordinator.

Calculation and plotting of this additional data need not be performed at this time.

6. 12. 3 NOTE 2:

The Test Coordinator will determine the operability status of any sensor.

Continue with recording and data calculation on at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> intervals for the Type A test period.

Maintain graphs of the items listed in step 6..12.4 et al.

6.12.4 6.12.4 '

6.12 '

6'2 '

6.12 '.4 Graphs of the following will be maintained:

Mass weight in Containment vs. time.

Containment average temperature vs. t'ime.

Containment dew point temperature vs. time.

Containment Pressure vs. time.

RSSP-6. 0: 19 The ILRT Test coordinator will evaluate the data and calculated leak rate to determine interim acceptability of the data for the Type

<<A>> Test period.IAW procedure Test Requirements.

Mass Point:

L. S ~ F.

95% U. C. L.

Total Time:

L. S ~ F.

954 U. C. L.

VERIFICATION TEST:

'NOT If CAM alarms aftei initiating the known.

leakage rate in the next step, terminate release and obtain sample for evaluation of radioactivity level.

Ensure a

CAM has been set up in vicinity of ILRT Panel by HP Dept.

and is operating.

Upon receiving permission from the ILRT Test Coordinator a known additional leakage rate (approx.

equal to LT) is to be established through the test flowmeter.

NOTE:

See Attachment B for calculation.

Data collection and calculations as well as the graphs of step 6.12.4 are to be maintained for at least the next 4

hour's or half the Type A test duration if the Total Time method is used for test termination.

Observe the frequency of step 6.12.3.

The ILRT Test Coordinator will evaluate the data and interim acceptability of the Type A test using the following formula:

(L

+ Lt 0.25 Lt)<L <(L

+ Lt

+ 0'5 Lt) where:

I

= Superimposed leakage rate between 75 and 125%'f Lt Lt

= Type A results tm L

= Verification test results c

~,

4, 0

0

RSSP-6.0:20 6'4 6'4 F 1 Notify Structural Engineering to prepare for taking radial displacement measurements.

6. 14. 2 Establish communications with Control Room to ensure personnel are available to maintain RCS Level control

~ as per steps 4.0 to 4.1 of Attachment E.

6.14.3 6 '4.3.1 6'4 '.2 The Containment atmosphere will be exhausted to outside atmosphere through the ILRT depressurization lines (MOV 7444)

(AOV 7445 and 7478) and (Test valve at. Penetration g2, if installed) as follows:

Using the control switch at the ILRT Instrument

Panel, slowly throttle Open MOV 7444 until a flow rate of approximately 7 psig/hour (not to exceed 10 psig/hour) is established.

~CAU IUN:

Prior to removing Test Tags from drains or vent valves, ensure that, these valves are closed and capped/flanged.

Initiate re-alignments utilizing RSSP-6.1, 6.2 and 6.3 as directed by the ILRT Test Coordinator.

CAUTION:

In order to prevent overshoot of the Hold Point limits in the next. step, at a Contain-ment pressure of approximately 16 psig begin throttling MOV 7444 closed.

6.14.3.3 Upon reaching a

Containment pressure of 15 psig,

+

.25 psig, MOV 7444 shall be closed to maintain this pressure for approximately one hour to allow Structural Engineering to perform radial displacement measure-ments.

6.14.3.3.1 Structural Engineering has notified ILRT Test Coordinator that measurements are complete.

6 '4.3.4 Throttle Open MOV 7444 to re-establish a flow rate of approximately 7 psig/hour (not to exceed 10 psig/hour).

CAUTION:

Estab' sh temporary personnel sa fety barriers prior,to next step.

RSSP-6.0:21 6.14.3.5 gggg:

If temporary test valve not installed, mark step 6.14.3.5 inclusive N/A.

When Depressurization flow rate can no longer be maintained at -7 psig/hour through MOV 7444 perform the following to align temporary test'valve:

(Mark these steps N/A if path not to be used) 6.14.3.5.1 Open vent valve on blank flange downstream of temporary Test valve at Penetration g2 to release any trapped air pressure.

6.14.3.5.2 Request Pipefitters to remove blank flange.

6.14.3.5.3 Slowly start opening temporary

Test, valve at Penetration g2.

I 6.14 '.6 To allow re-establishing Instrument Air to Containment and opening Depressurization flow path AOV 7478 and 7445, perform the following:

(Mark these steps N/A if path not to be used) 6.14.3.6.1 Close V5410B, IA Isol, and replace tubing cap.

6.14.3.6.2 Open V5397, Inst. Air Cnmt. Isol.

6.14.3.6.3 Place control switch for AOV 834B to the Open position.

NOTE:

This will close temporary vent path for Instrument Air line downstream of CV 5393.

6.14.3.6.4 Reset Containment Isolation Signal at MCB.

6.14.3.6.5 Reset AOV 5392 at the Containment Isolation Auxiliary Relay Panel (Train A

& B).

6.14.3.6.6 Reset AOV 7445 (Train A) at the Containment Isolation Auxiliary Relay Panel.

6.14.3.6.7 Reset AOV 7478 (Train B) at the Containment Isolation Auxiliary Relay Panel.

6.14.3.6.8 When Containment pressure is at =3 psig open AOV 7445 and AOV 7478 to provide an additional vent path to atmosphere.

S

RSSP-6.0:22 Notify the Shift Supervisor when depressurization of Containment.

has been completed.

Notify Structural Engineering Representative when depressurization of Containment has been completed to complete RSSP-6.5 and final radial displacement measurements.

Close the following States blocks which were opened in step 6.10.4.

CI-A2 Cabinet (Rear)

TB-1 States Block g61 MOV 7443 TB-1 States Block g65 MOV,7444 CI-B2 Cabinet (Rear)

TB-1 States Block f61 MOV 7443 Closed Verified Closed Verified Closed

'Verified TB-1 States Block f65 MOV 7444 Closed Verified Inform Operations that systems are available for alignment compatible with anticipated Plant operation.

l Notify Operations to insure all affected valves and equipment on Containment Isolation Reset Panel have been reset.

Notify Fire Protection that fire system Z-16 must be reconnected for return to service.

ILRT Events Log may be terminated at this time.

This record must be attached to completed RSSP-6.0.

Obtain the 'following post test levels and record on At".achment D.

Net changes in these levels will be evaluated for their effect on Containment free. volume and the necessity to apply corrections to the final test results:

6'0.1 RSSP-6.0:23 CONTAINMENT SUMP A LEVEL - MCB Indicators.

LI 2039 LI 2044 6.20 '

CONTAINMENT SUMP B LEVEL Dip stick method.

6 '0.3

'6.20.4 6.20.5 PRESSURIZER COLD CALIBRATION LEVEL MCB Indicator; LI 433 REACTOR COOLANT DRAIN TANK LEVEL WDP.

LI 1003 PRESSURIZER RELIEF TANK LEVEL MCB Indicator.

LI 442 COMMENTS:

COMPLETED BY:

DATE COMPLETED:

HEAD CONTROL OPERATOR:

SHIFT SUPERVISOR:

RESULTS 6 TEST REVIEW:

DATE:

II II INS ENTA ON CALIB ION DATA RSSP-6.0:24, E UIPMENT CALIBRATION DATE

RSSP-6.0:25 It II VERIFICA ON TEST Example:

(257,323 x.001528)

1440 =.273 lbs/min Convert pounds per minute to SCFM.

Example:

.273

.07517

= 3.63 SCFM Induce approximately that flow on the flowmeter through valve adjustments.

The tolerance is + 25% from previous example:

between 2.72 to 4.54 SCFM.

NOTE:

From the Containment

Mass, estimate the induced flow of LT in terms of pounds per minute.

0

RSSP-6 ':26 KXS S

TAG PREPARATION IST:

DEVICE V-886A V-886B V-535 PCV-430 PCV-431C LDCATION Art ACCUM IN CNMT B" ACCUM IN CNMT P

S ZER PRESSURIZER SSURIZ AS FOUND TEST POSITION OPEN-FIANGE REMOVED OPEN-FLANGE REMOVED OPEN FLANGE REMOVED OPEN BIDCKED 0

BIDCK HUNG CLEARING)

P -945 P -946 P -947 P -948 P -949 P -950 V-5397 V-5410 V-5410A V-5410B V-5394 V-5395 V-7440 MOV-7443 V-7435 V-7437 TGIAp Test Vlv.

RELAY ROOM RELAY 'ROOM RELAY ROOM RELAY ROOM RELAY ROOM RELAY ROOM PEN-310a, INT. N PEN-310a, INT. N PEN-310a, INT. N PEN-310a, INT.

PEN-310a, IN-CNMT PEN-310a, N-CNMT PEN-317 INT.

N PEN-317 INT.

N TURB.

BLDG. BSMT.

PEN-317 INT. N PEN-2; BY UIP.

HATCH FUSE PULLED FUSE PULLED FUSE PULLED FUSE PULLED FUSE PULLED FUSE PULLED CIDSED -

ARFI'PEN OPEN OPEN CAP REMOVED ARFT OPEN CIDSED CAPPED OPEN-ARFT CIDSED-ARFT CIDSED-ARFF OPEN

RSSP-6.0:27 1)

Containment Sump A PRE-TEST POST TEST 2) 3)

4) 5)

(LI 2039)

(LI 2044)

Containment Sump B

(Dip Stick)

Pressurizer Cold Cal.

Level (LI-433)

Reactor Coolant Drain Tank (LI-1003)

Pressurizer Relief Tank (LI-442)

COMPLETED BY:

DATE COMPLETED:

J 0

RCS L CO OL RSSP-6.0:28 Page 1 of 6

1.0 PURPOSE Provide Operations with a means of fillingthe RCS to a Pressurizer level of < 50%,

and maintaining Pres-surizer level in a band of 30-504 while Containment is under pressure testing.

I t'al Co d'tions:

1 ~ 1 ~ 1 1.1.2 1 ~ 1.3 1.1.4 RSSP-6.0 has been started.

Hose has been attached to Reactor Head Vent valve and directed to the lower cavity.

Hose Attached to V-500A At least one PORV is Blocked Open, or Pressurizer Manway is removed.

(N/A options that do not apply)

PRZR PORV PCV-431C Blocked Open PRZR PORV Block VLV MOV-515 Open PRZR PORV PCV-430 Blocked Open PRZR PORV BLOCK VLV MOV-516 Open Pressurizer Manway Removed RHR in normal cooling alignment.

2.0 F 1 2'-1 2 '

2 ~ 1.3 2 ~ 1 ~ 4 INITIALVALVE ALIGNMENT:

Pressurizer:

Open lower isolation valve to LT-426.

V-534 Open Open lower isolation valve. for LT-427.

V-509 Open Close AND cap valve for LT-427.

V-509A Closed V-509A Capped Open lower isolation valve for.LT-428 and LT-433.

V-511 Open 2.1.5 Close AND cap drain valve for LT-428 and LT-433.

V-511A Closed V-511A Capped

~ ATTA E RCS L CONTROL RSSP-6.0:29 Page 2 of 6 2.1.6 2.1.7 2.1.8 F 1.9

2. 1. 10 2.1.11 2 ' '2 2 ' '3 2 '.13 F 1 2.2 2'.1

~

2'.2 Open upper isolation valve for LT-428 and LT-433 and PT-431.

V-512 Open Open level column vent, valve.

V-537 Open Open upper isolation valve for LT-427 and PT-430.

V-510 Open Open level column vent valve.

V-536 Open Open upper isolation valve for LT-426, PT-429 and PT-.

449.

V-533 Open Open isolation valve for PT-430.

I V-12425 Open Open level control vent valve.

V-549C Open Reactor Head:

Open or lock open Reactor Vessel Head Vent valves.

V-500 Locked Open V-500A Open RWST to RHR suction fillalignment:

Stop Refueling Water Purification Pump.

Close inlet isolation to NRHX.

V-204A Closed 2 ' '

2.2.4 Close Refueling Water Purification Pump discharge isolation valve.

V-810 Closed Close Letdown suction isolation valve to Refueling Water Purification Pump.

V-820 Closed 2.2.5 Close suction block valve to Refueling Water Purifi-cation Pump.

V-824 Closed

P

RSSP-6.0:30 ACIDULENT E RCS LEVEL CO O

Page 3 of 6 2.2. 6 2 '

2.2.8 2.2.9 Close Letdown Deborating DI A&B outlet isolation valve to Letdown DI Filter.

V-247 Closed Close Letdown DI Filter drain valve to WHT.

V-251 Closed Close Letdown DI Filter outlet valve.

V-253 Closed Close Letdown DI Filter bypass valve.

V-250 Closed 2 ' '0 2 ~ 2 ~ll 2.2.12 2.2. 13 2.2.14 2.2.15 2.2.16 2 ~ 2 ~ 17 2 ~ 3 Open inlet block valve to Letdown DI Filter.

V-249 Open Open inlet block valve to PCV-135.

V-204C Open Open PCV-135 outlet block valve.

V-204E Open Open Letdown DI Filter.outlet block valve to RHR'Pump suction.

V-252 Open Place TCV-145 to the Divert position.

(MCB) TCV-145 in Divert Position Place PCV-135 in Manual Open.

(MCB) PCV-135 In Manual (MCB) PCV-135 Open Open Refueling Water Purification Pump discharge isolation valve to CVCS.

V-819,Open Open "Refueling, Water Purification Pump discharge isolation valve to CVCS.

V-821 Open Ensure MOV-857A, 857B, and 857C are operable and closed.

MOV-857A Closed MOV-857B Closed MOV-857C Closed

0 r

. 2.4 2 '

2.6 2.6

~ 1 2'.2 2 ' '

2 ~ 6.4 2 ' '

2.6.5.1 2.6.5.2 2 ' '.3 2 ~ 7 RSSP-'6.0:31 RCS LEVEL CO 0

Page 4 of 6, Open RWST outlet to CNMT Spray

& Safety Injection Pumps MOV~s; MOV-896A Open MOV-896B Open Ensure MOV-856 is operable.

Perform the following to fillPressurizer to < 504 WHEN directed by Shift Supervisor or Test Coordinator.

Establish CONTINUOUS communications with AO at MOV-856.

Communications Established'ocally throttle open MOV-856 to desired fillrate.

MOV-856 Open Station an AO with a Locked Valve Key near top of Cavity to perform the next step BEFORE 20% Pressurizer

level, (30" cold calibrated),

is reached.

Locked Valve Key Obtained AO Stationed at the Cavity Pressurizer Level

(<

20%

NR)

WHEN a steady stream of water comes out, THEN close the Reactor Vessel vent.

V-500A Closed Close the following Loop A Refueling Level Indicator manual isolation valves.

Loop A outer isolation valve to Refueling Level Indicator.

V-523 Closed Loop A inner isolation valve to Refueling Level Indicator.

V-524 Closed Loop A Tygon Hose Connection valve.

V-525 Closed WHEN Pressurizer level reaches just less than 50%,

THEN shut MOV-856 electrically.

MOV-856 Closed

e 0

'k

RSSP-6.0:32 C5iM%24T E RCS CO 0

Page 5 of 6 EMOTE:

NOTE:

Careful coordination between Control Room and the Test Coordinator is needed to maintain Pressurizer level between 40-50%

while CNMT is being pressurized/depressurized due to fill/dewatering rates achievable.

During Containment pressurization the suction pressure for the RHR pumps will increase to a point where it will exceed the 'elevation head from the RWST.

The Refueling Water Purification Pump will provide the additional pump head to allow filling from the RWST. If the RWPP should fail, or at any time pressurizer level cannot be maintained within the required band, notify the ILRT Test Coordinator to.'top the Containment pressure increase.

If level cannot be recovered, depressurize Containment to allow filling from the RWST through MOV 856.

3.0 When level makeup is required during Containment pressurization, then have AO locally throttle open MOV-856 to desired fillrate.

3 '

3.1.1 3 ' '

When level makeup through MOV-856 is no longer

possible, then have the auxiliary operator perform the following:

Open RWST suction isolation to Refueling Water Purification Pump.

V-808 Open Open Letdown DI Filter isolation valve to RHR Pumps suction.

V-822A Open 3 ~ 1.3

3. 1.4 Start Refueling Water Purification Pump as directed by Control to maintain Pressurizer level between 40-50%.

Refueling'ater Purification Pump Started Close MOV-856.

CS L CO O

RSSP-6.0:33 Page 6 of 6

• • • • • • • • @**a**a***************a*********~***4************4**

CA1~'ON:

WHEN draining to <204 Pressurizer

level, realign Refueling Level Indication that, was isolated in step 2.6.5.

CAUTION:

Observe that RHR total flow through PI-626 and FI-931B do not exceed 1500 GAL/MIN per pump-

%********4*******4**4***4*4*4k**4**************************

4.0 4.1

~F dewatering is necessary due to CNMT depres-surization, THEN coordinate with AO to manually throttle open MOV-857B to lower Pressurizer level to desired level.

MOV-857B Throttled Open WHEN desired level is reached, THEN close MOV-857B electrically.

MOV-857B Closed

)

RSSP4.0:34 Page i of 3 AS-FOUND VERSUS AS-LEFT MINIMUMPATHWAYLEAKAGERATE PIT PROC. NO.

23.1 23.2 23.3 23,5A 23.5B 23.6 23.8 23.9A 23.9B 23.10 23.11 23.12A 23.12B 23.12C 23.13A 23.13B 23.14 23.15 23.16A 23.16B 23.17A 23.17B 23.17C 23.18A 23.18B 23.19 AS-FOUND AS-LEFT DIFFERENCE (1)

"AS-FOUND" is the first LLRT result after plant shutdown.

(2)

"AS-LEFT" is the last LLRT result aAer all maintenance repairs, or just prior to performance of the ILRT.

COMPLETED BY:

DATE:

4 N

0

RSSP4.0:35 Page 2 of 3 AS-FOUND VERSUS AS-LEFT MINIMUMPATHWAYLEAKAGERATE FIT PROC. NO.

23.20 23.21 23.22 23.23 23.24 23.26 23.27 23.28 23.29 23.30 23.32 23.33 23.34 23.35.1 23.36.1 23.39 23.40 23.42 23.43 23.44 23.45 AS-FOUND AS-LEFT DIFFERENCE (1)

"AS-FOUND" is the first LLRT result after plant shutdown.

(2)

"AS-LEFT" is the last LLRT result after all maintenance repairs, or just prior to performance of the ILRT.

COMPLETED BY:

DATE:

RS SPA.0:36 Page 3 of 3 AS-FOUND VERSUS AS-LEFT MINIMUMPATHWAYLEAKAGERATE FIT PROC. NO.

23.46

.23.49 23.50A 23.50B 23.50C 23,51A 23,51B 23.51C 23.52 23.53.1 23.53.2 23,54 TOTAL AS-FOUND AS-LEFT DIFFERENCE (1)

"AS-FOUND" is the first LLRT result after plant shutdown.

(2)

"AS-LEFT" is the last LLRT result after all maintenance repairs, or just prior to performance of the ILRT.

, COMPLETED BY:

DATE:

4

RSSP4.0:37 TYPE A TEST RESULTS Least Squares Fit Leak Rate (LQ 95% UCL Leak Rate LLRT (Type B & C) Adjustments Other Adjustments (Repaired Valve Leakage Total (Lines 2, 3, &4)

Least Squares Fit Leak Rate (LQ 95% UCL Leak Rate LLRT (Type B &, C) Adjustments Other Adjustments (Repaired Valve Leakage)

Total (Lines 2, 3, &4)

4

~

0 RSSP-6. 0: 38 DATA SHEET 1

OUTER CONTAINMZÃP AREA PRESSURE READINGS DATE/TIME P

R E

S S

U R

E MECH MANIFOLD B PI 2292 MECH MANIFOLD A PI 2291 MECH MANIFOLD C PI-16

~ MECH MANIFOLD I PI 2281 EQUIP HATCH PI 2223 COMPLECTED BY:

DATE

RSSP-6..0:39 INNER AUXILIARYAREA PRESSURE READINGS DATE/TIME P.

R E

S S

U R

E PERSONNEL HATCH PI 2936 MECH MANIFOLD D PI'285 MECH MANIFOLD E PI 8 MECH MANIFOLD H PI 3 MECH MANIFOLD F PI 2282 MECH MANIFOLD G PI 2286 MECH MANIFOLD Z PI 6 MECH MANIFOLD K PI 6083 COMPIZTED BY:

fl

METEOROLOGICAL DATA DATE/TIME BAROMETRIC PRESSURE WEATHER CONDITIONS COMPLETED BY:

No:

93: 104 o

A-805: 17 F IBURE 04 CONSUMABLE MATERIAL CONTROL SYSTEM RESTRICTED-USE PERMIT (CORROSION CONTROL)

G INNA NUCLEAR STATION Y APPROVED FOR USE WITH RESTRICTIONS The following consumable product exceeds the maximum allowable concentration for contaminants.

(Dept/Shop)

SENSING SYSTEMS CORP requests approval to Use the product below for the (Bldg/System)

I AUX 8r INTERMEDIATE BLDG / ILRT SUPPORT

repair, maintenance, and/or modification described below!

I PRODUCT

LOCTITE FAST CURE EPOXY 45 I

OUANTITY DESCRIPTION OF USE

' \\

TO BE USED TO ATTACH BACK SITES FOR RADIAL DISPLACEMENT MEASUREMENT.

(Chemical Control Coordinator)

RESTRICTIONS FOR USE EPOXY IS APPROVED FOR THE ABOVE APPLICATION PROVIDED THE ONLY SURFACES CONTACTED ARE CONCRETE OR STRUCTURAL STEEL.

NO CONTACT IS TO BE MADE WITH ANY OTHER SURFACE COMPONENTS OR FLUID SYSTEM.

DO NOT STORE OR LEAVE EPOXY UNATTENDED IN PLANT WORK AREAS.

APPROVED BY (Chemical Co r

rdinator DATE:

Technical

Report, 50016-7 APPENDIX' RAW DATA

I h

0 4

I

R. E. GINNA NUCLEAR POWER PLANT Containment Building Radial Displacement Measurements Azimuth 40'2'ATE D/M/Y TIME H/M PRESSURE PSIG SCALE READINGS (inches)

ELEVATION (feet) 260'88'15'37'-

Il-8 4}-lx-qp ol I5 0 6>>0 1

1 O3 g

g~

6 I 5o 6'o f, I50 I) 6' p.~

g) 5; z.ay 5; w6'7 d

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R. E. GINNA NUCLEAR POWER PLANT Containment Building Radial Displacement Measurements Azimuth 166'7'VX

.bio~.

C DATE D/M/Y TIME H/M PRESSURE PSIG SCALE READINGS (inches)

ELEVATION (feet) 8PE/%3

/0: 35 (llsal~

l%.: 'Is Z~: 50 260'88',q'I s

315'.~56 3.357 337'.S6g 5.0IS 5,0EO

5. l3'I S,OSO Q. l2.>

s.lqO

3. WOS

,'I>0 3,532 s.&(0

3. (90 5 ~ho

4

R. E. GINNA NUCLEAR POWER PLANT Containment Building Radial Displacement Measurements Azimuth 260'0'gfgp,ddg7g8g 8L86.

+of s/48 SCALE READINGS (inches)

DATE D/M/Y TIME H/M PRESSURE PSIG ELEVATION (feet) 0 II f>

7:~5 9:15 g5: fo 260'.97m 5.575 288'.

ZO5 S.ZOs 5.zo5 315'37'I.OOy f): ()5 6;506 5.6(R

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0

Technical Report 50016-7 APPENDIX C CALIBRATION CERTIFICATES

I e

t C

I

KARA CO., INC.

SURYEYI 4400 RIVGRSI 708MMO'IO gG EQUIPMENT SALES 5 SERVICE PEAVEY

. LYONS, IL60534

~ ln IIjlnols 800-942-9382 'ax 708-442-73S9 CALIBRATIONCERTIFICATE I instrument submitted by:

8 E 5 I 8 S

tt'7

. 5 GO Descriptian:

5RLIkEOhl 75 S/aI 595'2.

We certify that the above instrument has been calibrated and I

adjusted ta campiy with the manufacturers specificatians.

We further certify that the referenced equipment has been inspected and calibrated with instruments whose basic I

accuracies are traceable to the National Bureau of Standards.

I Furthermol'e, ail the tests performed, fully comply with those used by the National Bureau of Standards.

By:

KARACo., inc.

Date:

I9.93 N.B.S. No:

e

KARA CO., lNC.

SURVEYIhfG EQUIPMENT SALES 8 SERVICE 4400 RIVERSIDis AVELYONS,II.60534 708-4424010 4 in illinois 800 942-9382 e Fax 708-442.7850 I

I I

CALIBRATIONCEFtTIRCATE Instrument submitted by:

BK S tPJG 5 RT 5

Dessription:

CE'i IQZte

@/her 05 77iG It We certify that the above instrument has been calibrated and adjusted to comply with the manufacturers specifications.

We further certify that the referenced equipment has been inspected and calibrated with instruments whose basic accuracies are traceable to the National Bureau of Standards.

Furthermore, all the tests performed, fully comply with those used by the National Bureau of Standards, By:

KARACo., inc.

Dste:

5 )9 99 M.s.s. Nn: 'alt',29929-R'S TOTAL P.esl

KARA CO.

INC.

l SURVEYING EQUIPMENT SALES & SERVICE 4400 RIVHRSI06 AVE., I.YONS, IL60534 7084$ 240I 0 j In Il)irtob800-942-9382

~ Fax 708-442-7359 II I

CAUBRAT)ON CERTlFiCATE instrument submitted by.'EM ~IPJG 5 57EMC

==

Description:==

~K

/OK 5/nJ 1

We certify that the above instrument has been calibrated and I

adjusted to comply with the manufacturers specifications.

We further certify that the referenced equipment has been inspected and calibrated with instruments whose basic I

accuracies are traceable to the National Bureau of Standards.

Furthermore, all the tests performed, fully comply with those used by the National Bureau of Standards.

By:

KARACo., Inc.

Date:

N.Et.a. No:

3Z 2298 19

e 0

Technical Report 50016-7 APPENDIX D TEST PERSONNEL

Technical Report 50016-7 Test Personnel:

Rochester Gas and Electric Co.

Leonard Sucheski, P.E.

John J. Ferraro, P.E.

Sensing Systems Corporation LaVerne F. Wallace Ricardo J.

Bermudez