ML20082H172

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Rev 5 to Procedure Dts 1600-7, Integrated Primary Containment Leak Rate Test
ML20082H172
Person / Time
Site: 05000000, Dresden
Issue date: 02/28/1983
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20082H066 List:
References
FOIA-83-384 DTS-1600-7, NUDOCS 8312010046
Download: ML20082H172 (77)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

"l, DTS 1600-7 Revision 5 February 1983 UNIT 2/3 INTEGRATED PRIMARY CONTAIfMENT LEAK RATE TEST A.

PURPOSE The purpose of this procedure is to detail the steps necitssary to detennine the integrated primary containment leak rate (Type A Test).

B.

REFERENCES 1.

Dresden Nuclear Power Station Units 2 & 3 Final Safety Analysis Report.

2.

10 CFR Part 50, Appendix J. January 1975 - Primary Reactor Containment Leakage Testing For Water-Cooled Power Reactors.

3.

ANSI N45.4 - 1972 - Leakage-Rate Testing of Containment Structures for Nuclear Reactors.

4 Bechtel Corporation Topical Report BN-TOP-1, Revision 1, November 1972 - Testing C:iteria For Integrated Leakage Rate Of Primary Containment Structures For Nuclear Power Reactors.

5.

Sargent and Lundy drawings:

a.

B-21, B-22, B-24, and 8-26.

b.

M-7 and M-8.

6.

Data Reduction & Error Analysis For The Physical Sciences, Phillip Bevington McGraw Hill.

C.

PREREQUISITES 1.

Notify shift prior to conducting integrated leak rate test.

2.

A signed and dated events log must be initiated by the respon-sible Tech Staff Engineer and will be kept up to date at all times by the Cognizant Engineer on shift.

3.

A familiarization by Tech Staff personnel of regulations, standards, and procedures applying to the ILRT including, but not limited to, those listed in REFERENCES.

4.

All local leak rate tests on valves, seals, and penetrations of the primary containment must be completed before the ILRT can begin.

2 46 830825 APPROVED GO GOL83-384 PDR FEB 16'83 1 of 77 p

D.O.S.R.

5 4 ~,m.

o

t t

l DTS 1600-7 Revision 5 NOTE Local leak rate tests must be done prior to and after any repair work being done on any penetration or associated isolation valve.

In the special case of double gas-keted seals, local leak rate tests must be done prior to opening the seal and after closing the seal.

5.

All pre-test checklist must be completed and returned to the responsible Tech Staff Engineer prior to the start of the test.

NOTE The work to be performed in these checklists involves various depart-ments within the station.

It also involves items which may be scheduled months or more in advance of the test.

It is the responsibility of the cognizant Tech Staff Engineer to schedule the items and coordinate the work so as to facil

' the execution of the ILRT.

6.

A?1 instruments to be used for the ILRT will be calibrated

(

over the full range of expected use prior to their placement in the primary containment for each test. The calibration must be in accordance with approved procedures.

7.

The pressure suppression chamber water level as monitored on LI-2(3)-1602-3 on panel 902(3)-3 should indicate approxi-l mately -3.0 inches.

8.

The reactor vessel water level as monitored on the WIDE RANGE GE-MAC (LI-2(3)-263-101), computer point F-286(386), should indicate approximately +50 inches.

9.

To maintain Reactor Water Level (+ 50 inches), open M0(2)3-1402-25A(B) valve with ECCS fill system pump running.

10.

Load and save the computer program on the computer if it is to be used.

11.

If it is desirable to have CPS available throughout the test, notify the Computer Systems Department at least two weeks in advance.

APPROVED 2 of 77 FEB 16 *83 D.O.S.R.

t

=

DTS 1600-7 Revision 5 12.

Prepare an instrumentation error analysis for the equipment used. See the example in Appendix A, attached.

13.

The test director will have on site a diagram or sensor placement within the containment and a simplified flow diagram of the It.RT computer program.

14.

Contact the American Nuclear Insurers Co. prior to perfeming l

the test.

D.

PRECAUTIONS 1.

Warning signs shall be pusted at convenient locations around the periphery of the test area. All personnel not perfoming any required duties shall restrict their access beyond these points.

2.

All station radiation protection and safety practicas and rules will be strictly followed for this test.

3.

All requests for equipment out-of-service for repairs during the test must be evaluated with respect to the fact that the primary centainment will be under approximately 48 psig.

4.

At no time during the period of pressurization, at test pres-sure, or depressurization of the primary containment will travel of the reactor building crane be allowed over the reactor cavity area.

5.

If use of the shutdown cooling system is anticipated at ;ay-time during the test, it shall be run for the entire duration of the test. This is to avoid transients in the vessel water level. A vessel water temperature of approximately 135*F shall be maintained.

\\

NOTE If shutdown cooling is run, one branch shall be put in service, but the vessel shell temperature shall not be allowed to drop below 120*F or go above 200*F and shall vary less than 5'F during the test.

When using shutdown cooling with the reactor recirculation pumps not running, either the recirculation pump suction valve (MO-202-4A or B) or discharge valve (M0-202-5A or B) and (MO-202-7A or 8) must be closed in order to insu*e that flow is es-tablished through the reactor ves-sel and not through the idle pump.

APPROVED 3 of 77 FEB 16'83 D.O.S.R.

s o

OTS 1600-7 8

Revision 5 E.

LIMITATIONS AND ACTIONS 1.

The integrated leakage rate test will be conducted by pressurizing the primary containment to a pressure of at least the calculated maximum peak a:cident pressure of 48 psig.

2.

After the preoperational leakage rate tests, a set of three type A tests shall be performed, at approximately equal in-tervals during each ten year service period. The third test of each set shall be conducted when the unit is shutdown for the ten year inservice inspections.

3.

Successful completion of this test will obtain all of the data necessary to demonstrate the integrity of the primary containment consistent with all station, license, and Nuclear Regulatory Commission requirements.

a.

The indicated leak rate shall be less than Lt (75% La).

b.

The upper 95 confidence limit of the indicated leak rate, whien includes appropriate consideration for ran-dom measurement errors, shall also be less than Lt (75% La).

4 Drywell pressurization will be discontinued if leakag: above the maximum allowable rate is obvious or the drywell pressure cannot be increased. Repairs will be made and the test re-started.

NOTE Before terminating the test, a leak rate must be determined for report-ing to tne NRC.

If the test is thus terminated, a Reportable Occurrence must be issued.

5.

During the period between the initiation of the containment inspectiori and the performance of this Type A test, no re-pairs or adjustments shall be made so that the containment can be tested in as close to the "as is" condition as prac-tical.

6.

During the period between the car.pletion of one Type A test and the initiation of the containment inspection for the sub-sequent Type A test, repairs or adjustments shall be rade to components whose leakage exceeds that specified in the Tech-nical Specifications as soon as practical after ide itification.

APPROVED FEB 16'83 4 of 77 D.O.S.R.

f 4

DTS 1600-7 Revision 5 7.

If ouring a Type A test, including the supplemental induced leakage test, potentially excessive leakage paths are iden-l tified which will interfere with satisfactory completion of the test, or which result in the Type A test not meeting the acceptance criteria, the Type A test shall be teminated and the leakage through such paths shall be measured using local leakage testing methods. Repairs and/or adjust:nents to equip-ment shall be made and the Type A test restarted. The cor-rective action and the change in leakage rate detemined from the tests and overall integrated leakage detemined from the local leak and Type A tests shall be included in the report submitted to the Cerimission.

8.

Closure of containment isolation valves for the Type A test shall be accomplished by normal operation and without any preliminary exercising or adjustments. Repairs of malopera-ting or leaking valves shall be made as necessary.

Informa-tion on any valve closure malfunction or valve leakage that requires corrective action before the test, shall be included in the report submitted to the Commission.

9.

The containment test conditions shall be allowed to stabilize for a period of at least four hours after initial pressurization.

Refer to Step F.2.g. (Pressurization and Stabilization).

10.

All vented systems shall be drained of water or other fluids to the extent necessary to assure exposure of the system con-tainment isolation valves to containment air test pressure and to assure that they will be subjected to the post-acci-dent differential pressure. Systems that are required to maintain the plant in a safe condition during the test shall be operable in their nomal mode, and need not be vented.

Systems that are normally filled with water and operating under post-accident conditions, such as the containment heat removal system, need not be vented. Refer to Table 1, list of non-vented systams.

11.

Results of the supplementai induced leakage test are accept-able provided that the difference between the supplemental test data and the Type A test data is within 0.25 La:

m i,,,

induced phase measured phase f,y "

  1. sed E.25 La L

calculated L

calculated

+L leak rate leak rate If results are not within 0.25 La, the reason shall be de 2 termined, corrective action taken, and a successful supple-mental test perfomed.

APPROVED FEB 16'83 5 of 77 0.0.S.R.

i

i DTS 1600-7 l

Revision'5 12.

A general inspection of the accessible interior and exterior surfaces of the primary containment stracture and components shall be perfomed prior to any Type A test to uncover any evidence of structural deterioration which may affect either the containment structural integrity or leak tightness.

If there is evidence of structural deterioration, Type A tests shall not be perfomed until corrective action is taken. Such structural deterioration and corrective actions taken shall be reported as part of the test report.

13.

If the shutdown cooling system is required due to the reactor decay heat, it shall remain in operation throughnut the test.

This will help prevent transients in reactor water level.

NOTE When using shutdown cooling with the reactor recirculation pumps not running either the recircula-or 8) pump suction valve (M0-20?-4A tien or discharge valves (M0-402-SA or B and M0-202-7A or B) must be closed in order to insure that flow is established through the reactor vessel and not through the idle pump.

14.

The Integrated Primary Containment Leak Rate Test will con-sist of five phases. Each phase will nave a definite starting and ending point and is so defined because of the different types of activities that will occur in each.

a.

The preparation phase (phase 1).

b.

The pressurization and stabilization phase (phase 2).

l c.

The measured leakage rate at 48 psig phase (phase 3).

l d.

The induced leakage phase at 48 psig (phase 4).

e.

The depressurization phase (phase 5).

NOTE The signed and dated events log started by the reponsible Tech Staff Engineer will be kept up to date at all times by the Cognizant Engineer on shift during phases (b) through (e), or as specified by the ILRT Test Engineer. Any changes to sen-sor location, instrumentation, or computer program must be entered into the ILRT log book under a sep-

' APPROVED arate section titled "Special Changes".

FEB 16'83 6 of 77 h.0. S. R.

075 1600-7 Revision 5 15.

Any change to instrumentation sensor ;1acement or computer progran must be reviewed at the same level as a temporary procedure change.

F.

PROCEDURE 1.

Test Preparation (PI)ase 1).

a.

Prior to sealing the drywell and pressure suppression chamber for pressurization, the pre-test portion of the following checklists must be completed:

CHECKLIST DEPARTMENT VERIFIED 1.

Maintenance 2.

Operations 3.

Instrument Mechanics 4.

Technical Staff Pretest preparation complete.

2.

Pres a ization ano Stabilization (Phase 2).

I a.

Complete steps F.2.a.1 through F.2.a.3 only if the 1.0 PSI drywell to torus vacuum breaker test is to be per-fomed.

(1) Perfom the vacuum breaker test per DTS 1600-16.

(2) After completion of DTS 1600-16, equalize the drywell to torus differential pressure; OPEN valves A0-2(3)-

1601-61 & 62.

(3) After equalization is achieved, CLOSE valves A0-2(3)-1601-61 & 62.

(4) Secure OPEN two sets (4) of vacuum breakers (Operating Dept).

(5) Begin pressurizing the containment for the ILRT.

b.

After the system is at least 2 psig, begin to inspect all appropriate penetrations and valves for excessive leakage. Special attention should be paid to the drywell to torus vacuum breaker position indications, electrical l

penetrations, and small penetrations which cannot be local leak rate tested.

APPROVED FEB 16 *83 7 of 77 D.O.S.R.

I

DTS 1600-7 Revision 5 c.*

If sources of leakage are found or the primary contain-ment instrumentation indicates excessive leakage, pres-surization should be stopped and this leakage should be estimated.

If repairs cannot be achieved without de-pressurization, the drywell and pressure suppression chamber should be vented to facilitate repairs.

NOTE The results of the local leak rate test or the estimated leakage rate from all reoaired leaks must be added tc the results of Type A test at 48 psig leak rate calcu-1ation to determine a leakage rate at the beginning of the test.

If this resultant leak rate is above La, a Reportable Occurrence must be initia ted.

d.

When at 15 psig hold for review of the leak rate as referenced by pressure decay indications.

e.

Resume pressurizing the containment until at least a pressure of 48 psig is obtained. Temperature stabilization may require additional pressurization until a balance is

achieved, f.

Remove pressurization flange at the drywell spray header and install the blind flange.

g.

Allow the containment atmosphere to stabilize until the following conditions have been met.

(1) The containment has been pressurized to greater than 48 psig at least four (4) hours or more.

AND (2) The rate of change of the average volume weighted temperature is less than 1.0*F/ hour over the last two (2) hours.

OR The rate of change of temperature changes is less than 0.5'F/ hour / hour averaged over the last two (2) hours.

APPROVED 8 of 77 D.O. S. R.

l DTS 1600-7 Revision 5 NOTE

' A continuous monitoring of the con-tainment penetrations should be maintained during the pressuriza-tion phase.

If any leaks are found, f

an estimate of the leakage rate must be made before any repairs are attempted.

I Containment stabilization complete.

h.

Perform local leak rate test, at 48 psig, on personnel interlock door per DTS 1600-14.

3.

Measured Leak Rate at 48 psig (Phase 3).

Either of the following methods may be used. Method A is preferred since it reouires a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> minimum test duration, whereas Method B requires a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> minimum test duration.

NOTE Calculation procedures for Method A are shown in Appendix A, C & D, those for Method B are shown in Appendix B, C & E.

n

- - ~..

Method A (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> minimum)hase 3 duration) a.

eck all accessible primary containment penetrations that exhibited leakage at 2 psig with soap solution before the start of data taking.

b.

Record the following data at least once every hour: 07

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IN }$.

(1) Time and date.

(2) Ambient temperature, pressure and relative humidity of the reactor building. (Data sheet 2 and 3).

(3) Absolute pressure of the primary containment. (Data sheet 4).

(4) Air temperatures inside the drywell and pressure suppression chamber. (Data sheet 1).

7 (5) Dew point temperatures inside the drywell and pressure j

suppression chamber. (Data sheet 1).

APPROVED FEB 16'83 9 of 77 D.O.S.R.

DTS 1600-7 Revision 5 (6) Reactor water temperature (Data sheet 2).

(7) Reactor water level. (Data sheet 2).

(8) Torus water level (LI-2(3)-1602-3 panel 902-3(903-3)).

(Data sheet 2).

c.

Calculate, using either the hand method (an example of which is in Appendix B & D attached) or with the aid of a computer, the following infomation at least once every hour.

(1) Average temperature by volume (*F)'.~-~~"

3 (2) Average vapor pressure by volume (psi).

(3) Average containment volume weighted temperature (*F).

(4) Average containment volume weighted vapor pressure (psi).

(5) Primary containment dry air pressure (psia).

(6) Mass of contained dry air (1bs).

(7) Total time measured leak rate (M ).

j (8) Calculated leak cate (L ) and 95% confidence limits.

g d.

Record the infomation in F.3.c. (Data sheet 4),

e.

Plot the infomation in F.3.c.(5) thru (8) as a function of time.

f.

Leakage rate measurements will be made at an average (over the time period of the test) containment pressure of at least 48 psig. Data taking will continue for at least 12 consecutive

hours, g.

From the third data set through the last data set, the percent leakage (measured) will be computed. The calculated leak rate is also computed by the Least Squares fit to the measured leakage data. The upper confidence limit of the calculated leak rate is then camputed.

h.

Compare the calculated leakage rate to Lt (1.2% per day) and La (1.6% per day).

If leakage rate approaches Lt every effort should be made to find the source of leakage and repairs made to stop it. The measured leak rate phase (Phase 3) should then be restarted.

APPROVED 10 of 77 D.O.S.R.

DTS 1600-7 Revision 5 1.

The measured leak rate phase can be terminated when all of the following criteria can be simultaneously verified:

(1) The containment atmosphere is stable. Refer to Section F.2.g. (Page 8) of this procedure.

Verified (2) The calculated leak rate is stable and less than 0.75 La.

Reference Topical Report BN-TOP-1, Section 2.3.B.1. if the calculated leak rate is increasing over time.

Verified (3) The last computed upper 95% confidence limit of the calculated leak rate based on Total Time calculations shall be less than 0.75 La.

Verified (4) The mean of the measured leak rates based on the Total Time calculations over the last five (5) hours of the test or twenty (20) data points, whichever provides the most data, shall be less than.75 L.

4 Verified (5) At least twenty (20) data points shall be provided for proper statistical analysis. The maximum interval between data sets shall be one (1) hour.

Verified (6) At least twelve (12) hours of data is available since the start of the measured leakage phase.

Verified J.

The measured leakage phase of the test has been successfully completed. Record below the calculated lenk rate for the last data sample.

Total Time Calculated Leak Rate

%/ DAY Verified Method B (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> minimum Phase 3 duration) a.

Check all accessible primary containment penetrations that exhibited leakage at 2 psig with soap solution before the start of data taking.

APPROVED 11 of 77 FB 16'83 D.O.S.R.

DTS 1600-7 Revision 5 b.

Record the following data at least once every hour:

(1) Time and date.

(2) Ambient temperature, pre::sure and relative hunidity of the reactor building. (Data sheet 2 and 3).

(3) Absolute pressure of the primary containment. (Data sheet 4).

(4) Air temperatures inside the drywell and pressure suppression chamber. (Data sheet 1).

(5) Dew point temperatures inside the drywell and pressure suppression chamber. (Data sheet 1).

(6) Reactor water temperature (Data sheet 2).

(7) Reactor water level. (Data sheet 2).

(8) Torus water level (LI-2(3)-1602-3 panel 902-3(903-3)).

(Data sheet 2).

c.

Calculate, using either the hand method (an example of which is in Appendix B attached) or with the aid of a computer, the following infomation at least once every hour.

(1) Average temperature by volume (*F).

(2) Average vapor pressure by volume (psi).

(3) Average containment volume weighted tenperature

(*F).

(4) Average containment volume weighted vapor pressure (psi).

(5) Primary containment dry air pressure (psia).

(6) Mass of contained dry air (1bs).

(7) Measured leak rate (weight %/ day).

(8) Linear least squares fit leak rate (weight %/ day).

d.

Record 'he infomation in F.3.c. (Data sheet 4).

e.

Plot the informatica in F.3.c.(5) thru (8) as a function of time.

APPROVED 12 of 77 FEB 16'83 D.O.S.R.

p DTS 1600-7 Revision 5 f.

Leakage rate measurenents will be made at an average containment pressure (over the time period of the test) of at least 48 psig. Data taking will continue for at least 24 consecutive hours.

g.

Canpare the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leakage rate to Lt (1.2% per day) and La (1.6% per day).

If the leakage rate tpproaches Lt, every effort should be made to find the source of leakage and repairs made to stop it. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> phase should then be restarted.

Phase 3 ends with the calculation of the 24th hourly set of information.

If the leakage rate is belcw Lt, at 48 psig, phase 4 can begin immediately.

If not, the responsible leaks must be repaired and the phase 3 repeated.

48 psig test phase successfully completed.

95% UCL (wt %/ Day), Calculated Leak Rate (wt%/ Day) i As Found Local Leak Rate (wt-%/ Day)

As Left Local Leak Rate (wt%/ Day)

Total Leakage Rate As Found/As Lef t

/

(wt %/ Day)

Verified 4.

48 psig Induced Leak Rate Phase (Phase 4).

i Phase 4 is the induced leakage portion of the ILRT. During this test, a deliberate leak of known magnitude will be su-perimposed on the leakage rate already calculated during the phase 3.

This will provide reassurance against any uncertain-ties associated with the performance of the leak rate test.

This leak should be of the same magnitude as phase 3 calculated leak rate.

ihe new leakage rate is then calculated and should approximately equal phase 3 leakage rate plus the induced leakage rate. This phase then acts as a verification of the accuracy of the data obtained in phase 3.

a.

The suction to the flowmeter for the induced leakage should be taken from the suction line to the CAM mon-Itor. The moisture separater can be installed if desir-able. The flowmeter discharge shall be vented to the reactor building.

b.

Request the Radiation Protection Department to obtain a drywell air sample. This can be obtained from the dis-charge of the ILRT flowneter.

(See Checklist #5, attached).

APPROVED Fa 16'83 13 of 77 D.O.S.R.

l DTS 1600-7 Revision 5 c.

In conjunction wth the air sampling, begin recording data as in step F.3.b. at least once every hour.

In addition to the above data, also record the induced leakage flow rate.

d.

Perfonn the calculations listed in step F.3.c. at least once every hour until sufficient data is obtained to adequately fulfill the requirements.

e.

If the induced leakage cannot be accurately detected, an investigation of the cause should be made, corrective actions taken, and the induced leakage pnase rescarted following repressurization to 48 psig. An evaluation and the corrective actions should be included in the report to the NRC.

I )

Superimposed Leak Rate: (g(a rl, SCFM 1440 MIN T+a59.69'R 14.696 PSIA 100% =

Day 519.69*R VOL WT*./ DAY p

WHERE, T = Induced phase average containment temperatu re,

  • F.

P = Induced phase average containment

pressure, PSIA.

VOL = Free volume of the containment.

ft3 Induced phase calculated leak rate:

WT%/ Day N

i _

7 L Induced Phase

-! L 24 Hr. Phase

+L Superimposed 4 0.25(1.6)

Calculated 1,eak Rate !

Calculated Leak Rate Leak Rate

~

$!.0.4T%/ Day

+

Induced leakage successfully detected.

5.

Depressurization (Phase 5).

Phase 5, the depressurization phase, can begin with the end of the successful completion of the induced leakage phase, a.

Isolate the ILRT flowmeter with local manual valves at flow meter.

b.

Verify that the results of the air sample taken in step F.4.b. a e below the allowable activity ifmits.

APPROVED 14 of 77 D.O.S.R.

OTS 1600-7 Revision 5 c.

OPEN valve A0-2(3)-1601-24.

d.

OPEN valves A0-2(3)-1601-61 and A0-2(3)-1601-62 and vent the containment through RX building vent.

1 e.

After depressurization is complete, normal staticn dry-well entry procedures should be followed for the initial drywell entry. One torus access hatch should be removed for torus entry.

f.

With the approval of the Rad Protection Department, the first subsequent drywell entry will be by Technical Staff personnel. The purpose of this entry is to note any deviation from original position of any instrumentation or fans used for the test. Any deviations found will be noted and accounted for in the log book.

g.

Only after the Technical Staff inspection will the In-strument Mechanics remova all test equipment from the primary containment.

~

h.

The responsible Tech Staff Engineer should notify the Shift Enginese of satisfactory completion of the test so that all valves with altered position status can be returned to normal, i.

CLOSE the torus access hatch after the renoval of all instrumenta tion. Tech Staff shall perform a final local leak rate test of that penetration.

Verified G.

CHECKLISTS 1.

DTS 1600-7, Mechanical Maintenance Department, Checklist 1, attached.

2.

DTS 1600-7 Electrical Maintenance Department, Checklist 2, attached.

3.

DTS 1600-7, Operating Department, Checklist 3, attached.

4.

DTS 1600-7, Instrument Maintenance Department, Checklist 4, attached.

5.

DTS 1600-7, Technical Staff, Checklist 5, attached.

6.

DTS 1600-7, Radiation Protecticn, Checklist 0, attached.

i i

H.

TECHNICAL SPECIFICATIONS REFERENCES 1.

Section 4.7. A.2.

APPROVED 2.

Section 3.6.B.2.

F816 *83 15 of 77 D.O. S. R.

DTS 1600-7 Revision 5 NECHANICAL MAINTENANCE DEPARTMENT CHECKLIST 1 A.

Pretest Requirements 1.

CLOSE equipment hatch and notify the Tech Staff to perform a local leak rate test.

Verified 2.

CLOSE both torus access hatches after verifying that the Instrument Mechanics have installed all the required in-s trumenta tion. Notify Tech Staff to perform local leak rate tes ts.

Verified 3.

Dry filtered air shall be supplied by air compressors to the drywell and pressure suppression chamber at penetration number X-150A.

Install the air compressors including piping, manifolds, af terfilters and dryers (or equivalent) to existing penetrations (refer to Figure 1 attached).

Verified 4.

After the drywell equipment drain and floor drain sumps are OUT-OF-SERVICE, remove the covers from check valves 2(3)-

2001-1A and 2(3)-2001-101A.

Inform the Shif t Engineer upon completion.

CAUTION Some contaminated water will spill when the covers are removed.

Verified:

B.

Post Pressurization Requirement Upon notification by the cognizant Tech staff person on shift, disconnect the 4" compressor discharge line and reinstall the regular drain piping and flange at penetration X-150A.

Verified C.

Post Test Requirement 1.

OPEN one torus access hatch.

Verified APPROVED O

16 of 77 D.O. S.R.

O DTS 1600-7 Revision 5 2.

Disassemble all the air compressor manifold piping.

Verified 3.

Upon the removal of all test instrumentation CLOSE the open torus access hatch and request Tech Staff to perform a local leak rate test.

Verified 4

RJplace the covers on the drywell equipment drain and floor drain sump discharge check valves 2(3)-2001-1A and 2(3)-

2001-101 A, and notify the Shif t Engineer.

Verified APPROVED FEB 16'83 s

,,f,7 D.O.S.R.

OTS 1600-7 Revision 5 ELECTRICAL MAINTENANCE DEPARTMENT CHECKLIST 2 i

A.

Protest Requirements j

s 1.

If fans are required in the torus and/or drywell, install them at the l

locations detemined by the Tech Staff Engineer.

]

Verified:

I installed not required 2.

Vent each indexer housing to the drywell.

Verified 3.

In order to prevent ECCS initiation following actions required.

Relay Panel Verification 590-103A 902(3)-15 Block in 12E2464 12E3464) 590-1038 902(3)-17 Block in 12E2464 12E3464) 590-103C 902(3)-15 Block in 12E2464 12E3464) 590-1030 902(3)-17 Block in 12E2464(12E3464)__

287-101A 902(3)-32 Lift Coil Wire 13 12E2461(12E3461) 287-102A 902 3 -32 Lift Coil Wira 13 12E2461 (12E3461) 287-1018 902

-33 Lift Coil Wire 13 12E2462 12E3462) 287-1028 902

-33 Lift Coil Wire 13 12E2462 12E3462) 1530-108 902

-32 Lift Coil Wire 13 12E2427 12E3437) 1530-208 902(3 -33 Lift Coil Wire 13 12E2438 (12E3438) 1530-109 902 3 -32 Lift Coil Wire 13 12E2437 12E3437) 1530-209 902 3 -33 Lift Coil Wire 13 12E2438 12E3438) 1530-134 902 3)-32 Lift Coil Wire 13 12E2437 12E3437) 1530-234 902 3)-33 Lift Coil Wire 13 12E2437 12E3437) 1530-199 902(3)-32 Lif9 Coil Wire 5 or dissonnect NN-36 12E2437(12E3437) 1530-299 902(3)-33 Lift Coil Wire 5 or disconnect NN-36 12E2438(12E3438) 8.

Post Test Requirements.

1.

Remove the fans (if installed) from the torus /or drywell after completion of the test.

Verified APPROVED c

FEB 16'83 18 of 77 D.O.S.R.

o DTS 1600-7 Revision 5 2.

Remove all the blocks and reconnect coil wires from the relays.

Relay Panel Verification 590-103A 902(3)-15 Block in 12E2464(12E3464) 590-1038 902(3)-17 Block in 12E2464 (12E3464) 590-103C 902(3 -15 Block in 12E2464(12E3464) 590-1030 902(3 -17 Block in 12E2464(12E3464) 287-101A 902 3 -32 Lift Coil Wire 13 12E2461 (12E3461) 287-102A 902 3 -32 Lift Coil Wire 13 12E2461(12E3461) 287-101B 902 3)-33 Lift Coil Wire 13 12E2462 (12E3462) 287-1023 902

-33 Lift Coil Wire 13 12E2462 (12E3462 1530-108 902

-32 Lift Coil Wire 13 12E2437 (12E3437 1530-208 902

-33 Lift Coil Wire 13 12E2438 12E3438 1530-109 902(3-32 Lift Coil Wire 13 12E2437 12E3437) 1530-209 902(3)-33 Lift Coil Wire 13 12E2438 12E3438) 1530-134 902(3)-32 Lift Coil Wire 13 12E2437 12E3437) 1530-234 902(3)-33 Lift Coil Wire 13 12E2437 (12E3437) 1530-199 902(3)-32 Lift Coil Wire 5 or disconnect NN-36 12E2437(12E3437) 1530-299 902(3)-33 Lift Coil Wire 5 or disconnect NN-36 12E2438(12E3438) 3.

Back to operation condition of indexer housing.

Verified APPROVED FB 16'83 19 of 77 D.O.S. R.

DTS 1600-7 l

Revision 5 OPERATING DEPARTMENT CHECKLIST 3 A.

Pretest Requirements 1.

The fol' owing items will be done in preparation for startup:

a.

Reactor recirculation loop System A, vented and water filled.

Verified b.

Reactor recirculation loop, System 8, vented and water filled.

Verified c.

Reactor recirculation loop cross tie header vented and water filled.

Verified __

2.

Prepare the primary containment isolation valves by positioning them as indicated on the attached list and hanging caution cards.

NOTE Closure of the containment isola-tion v.11ves will be done by the nomal mode of operation without preliminary exercising.

Verified 3.

Prepare the drywell equipment drain sump as follows:

a.

Pump down the drywell equipment drain sump as far as possible and then take the pumps OUT-0F-SERVICE.

b.

Close the sump pump discharge maintenance valves 2(3)-

2001-2A or 23 and then take OUT-OF-SERVICE.

c.

Notify maintenance to remove the cover from the sump pump discharge check valve out of service (refer to CHECKLIST 1. Step A.5).

d.

Clear the outage on the sump pump and verify manual discharge valve 2(3)-2001-2A and 2B are OPEN.

APPRO'JFD verified 93 1 6'B3 D.O.S R-

DTS 1600-7 Revision 5 4.

Prepare the drywell floor drain sump as follows:

(a) Pump down the drywell floor drain sump as far as pos-sible and then take the pumps OUT-OF-SERVICE.

(b) CLOSE the sump pump discharge maintenance valves 2(3)-

2001-102A or 1023 and then take OUT-OF-SERVICE.

(c) Notify maintenance to remove the cover from the sump pump discharge check valve out of service (refer to CHECKLIST 1. Step A.5).

(d) Clear the outage on the sump pump and verify manual discharge valve 2(3)-2001-102A and 102B are OPEN.

Verified 5.

Insure that the internal vessel atmosphere is vented to the drywell and interconnecting pressure suppression containment by OPENING 2(3)-220-48 and 2(3)-220-49 as a path to the dry-well equipment drain sump. Ensure that the bulkhead hatches are open.

Veri fied 6.

Isolate the jockey pump fra the appropriate LPCI loop by CLOSING the following valves:

MO-2

-1501-32A 2

-1501-66A Notify the maintenance department in order that the contain-ment spray header flange can be changed to accommodate the air line.

Verified 7.

Check that the TIP detectors are in their shields with each TIP drive mechanism primary power connector J-4 removed and logged in the Jumper Log. The TIP ball valves should be closed and taken out of service.

Verified 8.

Verify that both core spray loops are filled with water.

Verified 9.

Turn both CRD pumps off.

Verified APPROVED g16*B3

  • ' ' 77 D.O.S.R-l

DTS 1600-7 Revision 5 10.

If the reactor vessel water temperature can remain at approx-imately 135'F without the use of the shutdown cooling through-out the test duration, this system shall be isolated; other-wise, one loop shall be put into operation using both suction and discharge lines.

Verified:

SDC required SDC not required 11.

Imriediately prior to pressurizing the primary containment, make a general announcement over the plant public address system stating that the ILRT is about to begin.

Verified 12.

OPEN the VALVE 2-1501-28A(3-1501-288) for containment pres-surization.

Verified 13.

Turn off all drywell coolers.

Verified Performance of this checklist will put the systems affecting primary containment in the following configuration:

SYSTEM CONDITION Main Steam Isolated, Drained Vented Reactor Feedwater Isolated (Water filled, ready for operation)

Reactor Building Closed Cooling Supply closed, Return Open Water to Drywell Pressure Suppression Isolated, Vented Core Spray Isolated Low Pressure Coolant Injection Isolated High Pressure Coolant Injection Isolated Reactor Cleanup Isolated. Filter demin ready for service.

Shutdown Cooling Isolated, unless operation required to maintain 135'F reactor vessel water temperature.

Clean Demin to Drywell Isolated Drywell Floor & Equipment Drains Isolated, Vented Service Air to Drywell Isolated Drywell Pneumatic Isolated, Vented Isolation Condenser Isolated, Vented Reactor Recirculation Filled, Pumps Off Head Cooling Isolated, Vented CR0 Return Isolated APPROVED 22 of 77 FEB 16 '83 0.0.S.R.

DTS 1600-7 Revision 5

(

B.

Post Pressurization Requirements 1.

CLOSE VALVE 2-1501-28A(3-1501-288) upon notification from the Tech Staff.

Veri fied 2.

From now until the end of the test, maintain as constant as possible a water temperature of 135'F.

NOTE Once a suitable shutdown cooling )-

flow rate is established, the 2(3 1001-4 valves are not to be throttled.

All temperature control is to be done with the 2(3)-3704 valve and/

or the appropriate RBCCW manual shutdown cooling heat exchanger inlet valve.

Verified 3.

After the Maintenance Department removes the temporary flange from the containment spray line, OPEN the following valves:

M0-2(3)-1501-32A 2(3)-1501-66A Verified C.

Post Test Requirements 1.

Return all previously altered equipment back to its normal state.

Verified APPROVED FEB 16'83 23 of 77 D.O.S.R.

)

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SI7E VALVE NUMBER VALVE POSITION DESCRIPTION 12 105A 517-6 5

20 A0-2-203-1A C

Primary Steam A0-2-203-2A C

Primary Steam 3/4 2-220-7A C

(Gland Seal Leak-Off) 2-220-8A C

(Gland Seal Leak-Off) 2-220-9A C

Viv Body Drain) 2-220-10A C

Viv Body Drain)

C MSL Test Conn - 2 Valves) 12 1058 517-6 10 20 A0-2-203-1B C

Primary Steam A0-2-203-2B C

Primary Steam 3/4 2-220-78 C

Gland Seal Leak-Off) 2-220-88 C

Gland Seal Leak-Off) 2-220-98 C

Viv Body Drain) 2-220-10B C

(Viv Body Drain)

C (MSL Test Conn - 2 Valves) 12 105C 517-6 350 20 A0-2-203-1C C

Primary Steam A0-2-203-2C C

Primary Steam 3/4 2-220-7C C

(Gland Seal Leak-Off) 2-220-8C C

Gland Seal Leak-Off) 2-220-9C C

Viv Body Drair.)

2-220-10C C

V1v Body Drain)

C (MSL Test Conn - 2 Valves) 12 105D 517-6 355 20 A0-2-203-10 C

Primary Steam A0-2-203-2D C

Primary Steam 3/4 2-220-7D C

(Gland 5231 Leak-Off) 2-220-83 C

(Gland Seal Leak-Off) 2-220-90 C

VivBodyDrain) 2-220-10D C

V1v Body Drain)

C MSL Test Conn - 2 Valves) 12 106 515-0 2

MO-2-220-1 C

MSL Drain MO-2-220-2 C

MSL Drain 3/4 2-220-5 C

MSL Drain Test Conn 2-220-6 C

MSL Drain Test Conn 2

MO-2-220-90A 0

MSL Vent Path MO-2-220-908 0

MSL Vent Path MO-2-220-90C 0

MSL Vent Path MO-2-220-900 0

MSL Vent Path MO-2-220-3 0

MSL Vent Path 2-3025-500 0

MSL Drain Hose Conn) 2-3025-501 0

(MSL Drain Hose Conn) 12 115B 513-9 275 3/4 2-220-11A 0

MSL F1ow Instr.

2-220-12A 0

APPROVED 24 of 77 FEB 16'83 D. O. S. R.

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION l.INE DESIRED NORMAL P&ID NO.

ELEY. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 12 115B 513-9 275 3/4

-220-118 0

MSL Flow Instr 2-220-123 0

2-220-11C 0

2-220-12C 0

2-220-110 0

2-220-120 0

20 123 513-9 45 6

MO-2-3702 C

RBCCW Inlet 20 124 513-9 48 6

MO-2-3703 0

RBCCW Outlet MO-2-3706 0

25 131A 528-0 110 3/4 2-1601-4A 0

ECCS & Auto Blowdown Sensors 131B 115 2-1601-48 0

131C 290 2-1601-4C 0

1310 295 2-1601-40 0

25 12G 513-0 332 18 A0-2-1601-21 C

N Purge & Vent A0-2-1601-22 C

A0-2-1601-55 C

A0-2-1601-56 C

3/4 C

(TestConnection) 4 2-8599-544 0

(Pumpback Syst) 2-8599-545 0

135 MO-2-1601-57 C

N Make-Up A0-2-1601-58 C

A0-2-1601-59 C

1/4 2-8599-526 C

(TestConnection) 1 2-8599-558 0

(Pumpback Syst) 2-8599-552 0

25 304 509-0 270 18 A0-2-1601-20A C

Torus Vacuum Relief A0-2-1601-20B C

(NOTE: FAIL OPEN) 3/4 2-1699-50 C

(Test Conn - 2 Valves) 2-1699-51 C

(Test Conn - 2 Valves)

D/W Cooler Damper Control N Supply C

a 25 125 572-0 145 18 A0-2-1601-23 C

Drywell Vent A0-2-1601-24 C

2 A0-2-1601-62 C

6 A0-2-1601-63 C

3/4 C

(Test Connection 9 EL 570-0) 23 318 509-0 95 18 A0-2-1601-60 C

Torus Vent APPROVED 25 of 77 FEB 16'83 D.O.S.R.

u

OTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCAi!ON LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVF POSITION DESCRIPTION 25 318 509-0 95 2

A0-2-1601-61 C

Torus Vent 3/4 2-1699-002 C

(Test Connect 9 EL 509 2 Valves) 25 309A 498 7 155 1/2 FCV-2-8501-1A C

Torus Air Sample FCV-2-8501-1B C

25 204 532-6 190 1

FCV-2-8501-3A C

Sample Return t

FCV-2-8501-3B C

25 143 547-6 120 1/2 FCV-2-8501-5A C

Drywell Air Sample FCV-2-8501-58 C

FCV-2-9205A C

FCV-2-92058 C

FC_V-2-9206A C

FCV-2-9026B C

2-2252/47/1 C

(2 Valves) 2-2252/47/2 C

(2 Valves) 2-2252/47/3 C

(2 Valves) 2-2252/47/4 C

(2 Valves)

Z-2252/47/5 C

(2 Valves) 2-2252/47/6 C

(2 Valves) 2-2252/47/7 C

(2 Valves) 2-2252/47/8 C

2 Valves) 2-2252/47/9 C

2 Valves) 2-2252/47/10 C

2 Valves) 2-2252/47/11 C

2 Valves) 2-2252/47/12 C

(2 Valves) 2-2252/47/13 C

(2 Valves) 2-2252/47/14 C

(2 Valves) 2-2252/47/15 C

[2 Valves) 2-2252/47/16 C

2 Valves) 2-2252/47/17 C

(2 Valves) 2-2252/47/18 C

2 Valves) 2-2252/47/19 C

2 Valves) 2-2252/47/20 C

2 Valves) 2-2252/47/21 C

2 Valves) 2-2252/47/22 C

2 Valves) 2-2252/47/23 C

2 Valves (1 Valve))

2-2252/47/24 C

26 147 564-0 295 2h FCV-2-205-2-3 0

Rx Head Cooling M0-2-205-2-4 C

3/4 2-205-2-1 0

(Drain) 2-205-2-2 0

(Drain) 2-205-2-5 C

(Test Connection)

APPROVED 2-205-2-6 C

(TeseConnection)

FEB16'83 26 of 77 0.0.S A

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL l

P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 2-2099-323 C

Drain) 2-2099-324 C

Orain) 2-2099-325 C

Drain) 2-2099-326 C

(Drain) 2-2099-327 C

(Test Connection) 2-2099-328 C

(Test Connection) 26 135A 563-0 70 1

2-220-53 0

Rx Vessel Instr 127A 560-0 70 1

2-263-2-10 0

12BA 565-0 210 1

2-263-2-12B 0

1288 565-0 210 1

2-263-2-14B 0

129A 564-0 70 1

2-263-2-12A 0

129B 564-0 70 1

2-263-2-14A 0

129C 564-0 70 1

2-263-2-16A 0

1290 564-0 70 1

2-263-2-18A 0

2-263-41A 0

129E 564-0 210 1

2-263-2-168 0

129F 564-0 210 1

2-263-2-188 0

2-263-41B 0

142A 540-0 75 1

2-263-2-308 0

2-263-2-30C 0

2-263-2-300 0

2-263-2-30E O

2-263-2-30G 0

2-263-2-30H 0

2-263-2-30J 0

2-263-2-30K 0

2-263-2-21A G

2-263-2-21B 0

2-263-2-22A 0

2-263-2-228 0

37 136A-E 517-6 270 3/8 Tip Ball Valves (5)

C i

Tip Drive Power Breakers (2)

Racked Out i

Drywell 0 Anal.

2 Cab Skrs #1 Racked Out

  1. 2 Racked Out
  1. 3 Racked Out
  1. 4 Racked Out 1428 540-0 245 1

2-263-2-30M 0

2-263-2-30N 0

2-263-2-30P O

2-263-2-30R 0

2-263-2-30T 0

2-263-2-300 0

2-263-2-30V 0

APPROVED 27 of 77 0.0.S.R.

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 142B 540-0 245 1

2-263-2-30W 0

2-263-2-21C 0

2-263-2-210 0

2-263-2-22C 0

2-263-2-220 0

131A 528-0 110 1

2-263-2-24 0

1318 528-0 115 1

2-263-2-26 0

131C 528-0 290 1

2-263-2-32 0

146 541-0 105 1

2-220-66A 0

2-220-668 0

2-220-66C 0

2-220-660 0

208 536-0 205 1

2-220-66E O

2-220-6SF 0

2-220-66G 0

2-220-66H 0

133A 510-0 90 1

2-220-15A 0

1338 510-0 90 1

2-220-16A 0

133C 510-0 270 1

2-220-15B 0

1330 510-0 270 1

2-220-168 0

132A 510-0 90 1

2-262-2-4A 0

1328 510-0 90 1

2-262-2-3A 0

132C 510-0 270 1

2-262-2-4B 0

1320 510-0 270 1

2-262-2-38 0

134A 510-0 90 1

2-220-13A 0

1348 510-0 90 1

2-220-14A 0

134C 510-0 270 1

2-220-138 0

1340 510-0 270 1

2-220-148 0

26 122 548-8 265 3/4 A0-2-220-44 C

Rx Water Sample A0-2-220-45 C

2-220-102 0

2 220-42 C

(TestConnection) 2-220-43 C

(Test Connection) 2-220-48 0

(Head Vent) 2-220-49 0

(Head Vent) 27 149A 564-9 20 10 2-1402-6A 0

Core Spray 3/4 2-1402-35A C

(Drain) 2-1402-46A C

(Gland Seal Leak-Off) 2-1402-32A C

(Test Connection) 2-1402-33A C

13 MO-2-1402-25A C

3/4 2-1402-5A C

(Drain /TestConnection) 2-1402-52A C

(Drain /TestConnection)

APPROVED 2-1402-7A C

(Drain)

FEB 16'83 28 of 77 D.O.S ft

l DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 27 149A 564-9 20 3/4 2-1402-14A C

(Drain) l 2-1402-15A C

(PumpDrain) 16 M0-2-1402-3A 0

2-1402-29A 0

Manual Isol.

12 2-1402-2A C

2-1402-29B 0

Manual Isol.

27 149A 554-9 155 10 2-1402-6B 0

Core Spray 3/4 2-1402-35B C

Drain) 2-1402-46B C

Gland Seal Leak-Off) 2-1402-328 C

Test Connection) 2-1402-338 C

10 MO-2-1402-258 C

3/4 2-1402-5B C

(Drain / Test Connection) 2-1402-528 C

(Drain /TestConnection) 2-1402-78 C

(Drain) 2-1402-148 C

(Drain) 2-1402-15B C

(Pump Drain) 16 MO-2-1402-3B 0

12 2-1402-2B C

27 310A 509-0 118 8

M0-2-1402-4A C

Core Spray Test Line 3108 509-0 238 8

M0-2-1402-48 C

28 141A 542-6 160 14 M0-2-1301-1 0

Isolation Condenser MO-2-1301-2 0

3/4 2-1301-34 C

(Test Connection) 2-1301-35 C

(Test Connection) 2-1301-505 C

(Gland Seal-Leak Off) 2-1301-506 C

Gland Seal-Leak Off) 1 2-1301-21 0

Ins trumentation) 2-1301-22 0

Instrumentation 2-1301-27 0

(Instrumentation 2-1301-28 0

Instrumentatien 3/4 A0-2-1301-17 C

Vent) 2-1301-606 C

Drain) 2-1301-607 C

Drain)

A0-2-1301-20 C

Vent) 2-1301-14 C

Vent) 2-1301-15 C

Vent) 28 109A 547-10 178 12 MO-2-1301-3 C

(Isolation Condenser) 2-1301-600 C

(Vent) 2-1301-601 C

M0-2-1301-4 C

Drain) 3/4 2-1301-18 C

Drain)

APPROVED 2-1301-19 C

Drain) 2-1301-32 C

TestConnection) 2-1301-33 C

(Test Connection) fEB 16'83 29 of 77 p.O.S. R.

l DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 29 116A 513-9 83 16 MO-2-1501-22A C

LPCI Injection 2-1501-26A 0

1/2 2-1501-91A C

Drain) 2-1501-151A C

Test Connection) 3/4 2-1501-234 C

Test Connection) 2-1501-79A C

Vent) 2-1599-2A C

Drain) l 29 1168 513-9 263 16 MO-2-1501-22B C

LPCI Injection 2-1501-268 0

1/2 2-1501-918 0

(Drain) 2-1501-151B C

Test Connection) 3/4 2-1501-238 C

Test Connection) 2-1501-79B C

Vent) 2-1599-2B C

(Orain) l 29 310A 509-0 118 14 M0-2-1501-20A C

LPCI Test MO-2-1501-38A C

3/4 2-1501-87A C

(TestConnection) 2-1501-2A C

22A Valve Drain 29 3108 509-0 238 14 MO-2-1501-208 C

LPCI Test M0-2-1501-388 C

3/4 2-1501-878 C

(TestConnection) 2-1501-28 C

228 Valve Drain 29 145 547-6 210 10 MO-2-1501-27B C

LPCI DW Spray MO-2-1501-288 C

2-1501-298 C

l 3/4 2-1501-308 C

Test Connection) 2-1501-45B C

Vent) 29 150A

  • 527-1 160 10 MO-2-1501-27A C

LPCI DW Spray 2-1501-2BA C

i 3/4 2-1501-45A C

(Vent)

MO-2-1501-32B 0

2-1501-29A C

Test Connection 2-1501-30A C

Test Connection 29 311A 509-0 120 6

MO-2-1501-18A C

LPCI Torus Spray MO-2-1501-19A C

3/4 2-1501-40A C

(Drain / Test Connection) 29 311B 5 09 -0 240 6

MO-2-1501-188 C

MO-2-1501-198 C

3/4 2-1501-e64 C

(Drain / Test Connection) 29 14 MO-2-1501-5A 0

APc nv <S,4ction fMg MO-2-1501-58 0

c ti M0-2-1501-5C 0

MO-2-1501-50 0

FEB 16 '83 30 of 77 D.O.S. R.

{

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DCSIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 29 14 2-1501-31A C

2-1501-31B C

2-1501-31C C

2-1501-31D C

2-1501-66A C

ECCS Fill 2-1501-66B C

30 113 547-10 300 10 MO-2-1201-1 C

Rx Cleanup M0-2-1201-2 C

MO-2-1201-3 C

1/2 2-1299-4 C

(Drain / Test Connection) 2-1299-6 C

2-1299-6 C

2-1201-31 C

(Vent on Clean-Up Aux Pump) 2-1201-32 C

2-1299-11 C

CU Hdr Test Tap 32 111A 530-8 25 16 M0-2-1001-1A C

Shutdown Cooling 3/4 2-1001-88A C

(Gland Seal Leak-Off) 2-1001-46A C

(Drain) 2-1001-45A C

Drain) 14 MO-2-1001-2A C

PumpSuction)

M0-2-1001-2B C

Pump Suction) 3/4 2-1001-92A C

Drain / Gland Seal) 2-1001-928 C

Drain / Gland Seal) 2-1001-93A C

(Drain) 2-1001-938 C

(Drain) 2-1001-47A C

Vent 2-1001-48A C

Vent 32 1118 530-8 70 16 MO-2-1001-1B C

Shutdown Cooling 3/4 2-1001-888 C

(Gland Seal Leak-Off) 2-1001-468 C

(Drain) 2-1001-45B C

(Drain) 14 M0-2-1001-2C C

Pump Suction) 3/4 2-1001-92C C

Orain/ Gland Seal) 2-1001-93C C

Drain) 2-1001-478 C

Vent) 2-1001-488 C

Vent) 2-1001-200 C

32 116A 513-9 83 14 MO-2-1001-5A C

Shutdown Cooling 3/4 2-1001-14A C

(Gland Seal Leak-Off) 2-1001-10A C

2-1001-28A C

(Drain) 32 116B 513-9 263 14 MO-2-1001-5B C

Shutdown Cooling APPROVED 31 of 77 FEB 16 '83 D.O.S. R.

1

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VAI.VE NUMBER VALVE POSITION DESCRIPTION 32 1168 513-9 263 3/4 2-1001-148 C

(Gland Seal Leak-Off) 2-1001-10B C

2-1001-283 C

(Drain) 33 130 581-0 340 1-1/2 2-1101-1 0

SBLC 1/2 2-1199-104 C

(Drain) i 2-1199-105 C

2-1199-103 C

(TestConnection) 2-1199-102 C

2-1199-107 C

(TestConnection) 2-1199-106 C

34 144 547-6 150 3/4 2-301-96 C

CRD (Return Test Conn) 2-301-97 C

1/.

2-301-500 C

CR0 (Return Test Conn) 2-301-501 C

35 119 527-6 275' 3

2-4327-500 C

Well Water 37 112A 547-5 8

1/4 C

Drywell Cooler Damper Control (11 Valves) 1/4 C

(5 Valves) 1128 547-5 21 1/4 C

(25 Valves) 37 121 527-6 283 1

2-1601-48 0

CW Pneumatic AG-2-4722 C

1/4 C

(Test Connection by 4722) 2-4741-20C 0

(TestVent) 37 139D 537-6 280 1

A0-2-4720 C

DW Pneumatic A0-2-4721 C

1/4 C

(Test Connection between 4720 and 4721) 2-4771-500 0

(Test Vent) 2-4771-501 0

(TestVent) 38 120 527-6 280 3

2 A630-500 C

Service Air 3

2-4609-501 C

510-0 0

(Hose Conn Col H-42) 480-0 0

(Hose Conn Col G-42)

{

39 118 512-3 45 3

A0-2-2001-5 C

DW Equip Drain A0-2-2001-6 C

3/4 2-2005-506 C

(TestConnection) 3 A0-2-2001-3 0

39 117 512-3 185 3

A0-2-2001-105 C

DW Floor Drain APPROVED 32 of 77 FEB 16 *83 D. O. S. R.

1

e DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 39 117 512-3 185 A0-2-2001-106 C

DW Floor Drain 3/4 2-2001-500 C

(Test Connection) 49 561 18 MO-2-7503 0

U-2 Rx Bldg Normal Vent 51 115A 513-9 97 10 MO-2-2301-3 0

HPCI MO-2-2301-4 C

M0-2-2301-5 C

3/4 2-2301-16 C

2-2301-17 C

(TestConnection) 2-2301-72 C

(Gland Seal Leak Off) 1 50-2-2301-31 0

S0-2-2301-28 C

50-2-2301-29 C

S0-2-2301-30 C

2-2301-43 C

Test between A0-2301-29 and A0-2301-30 2-2301-44 C

51 141A 542-6 160 3/4 2-2301-24 0

HPCI Instrumentation 2-2301-25 0

51 317A 509-10 !90 3/4 2-2301-41A C

HPCI Cond Return 3/4 2-2301-42A C

(TestConn) 51 312 49 7-0 200 3/4 2-2301-41B C

HPCI Drain Pot Drain 3/4 2-2301-428 C

(Test Conn) 2 2-2301-33 0

2-2301-47 0

1 S0-2-2301-32 C

51 310A 509-0 118 4

MO-2-2301-14 C

HPCI Min Flow 51 16 MO-2-2301-35 C

HPCI Suction MO-2-2301-36 C

M0-2-2301-6 0

2-2301-93 C

Drain 2-2301-94 C

Drain 2-2301-37 C

Test Conn 2-2301-38 C

Test Conn 707 2048 532 195*

1" A0-2-2599-2B C

ACAD Sh 1 of 2 3/4" 2-2599-11B C

ACAD 3/4" 2-2599-12B C

ACAD APPROVED 2048 532 195*

1" 2-2599-258 0

ACAD i

33 of 77 D.O.S. R.

v DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 707 316B Torus 305 1"

A0-2-2599-38 C

ACAD Sh 1 3/4" 2-2599-148 C

ACAD of 2 3/4" 2-2599-13B C

ACAD 316A Torus 55*

1" A0-2-2599-3A C

ACAD 3/4" 2-2599-14A C

ACAD 3/4" 2-2599-13A C

ACAD 202V 534 165*

1" A0-2-2599-2A C

ACAD 3/4" 2-2599-11A C

ACAD 3/4" 2-2599-12A C

ACAD 1"

2-2599-25A 0

ACAD 1"

2-2599-21 ACAD AIR PRESSURE ACAD AIR COMPRESSOR OFF DRAIN 125 572 145' 1"

FCV-2-2599-4A C

FCV-2-2599-5A C

FCV-2-2599-4B C

FCV-2-2599-5B C

3/4" 2-2599-15A C

2-2599-16A C

2-2599-15B C

2-2599-168 C

707 202V 534 165*

1/2" 50-2-2499-2A C

CAM Sh 2 of 2 1/2" S0-2-2499-1A C

CAM 1/2" 2-2499-7A C

CAM APPROVED 34 of 77 FB 16 '83 D.O. S. R.

1

DTS 1600-7 Revision 5 UNIT 2 VALVE LINEUP (Cont'd.)

l PENT LOCATION LINE DESIRED NORMAL l

P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 707 1/2" 2-2499-8A C

CAM Sh 2 of 2 316A Torus 55' 1/2" S0-2-2499-4A C

CAM 1/2" S0-2-2499-3A C

CAM 1/2" 2-2499-10A C

CAM 1/2" 2-2499-9A C

CAM 204B 532 195*

1/2" S0-2-2499-2B C

CAM 1/2" S0-2-2499-1B C

CAM 1/2" 2-2499-78 C

CAM 1/2" 2-2499-8B C

CAM 316B Torus 305*

1/2" S0-2-2499-4B C

CAM 1/2" S0-2-2499-3B C

CAM 1/2" 2-2499-10B C

CAM 1/2" 2-2499-98 C

CAM APPROVED 35 of 77 D.O. S. R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 356 X115A 528-0 110 3/4 3-1601-4A 0

ECCS & AUTO Blowdown X-115B 115 3-1601-4B 0

X-127D 290 3-1601-4C 0

X-127E 29 5 3-1601-4D 0

353 X-123 513-9 45 6

MO-3-3702 C

RBCCW INLET 353 X-124 513-9 48 6

MO-3-3703 0

RBCCW OUTLET MO-3-3706 0

360 X-116A 513-9 83 16 MO-3-1501-22A C

LPCI INJECTION X-116B 253 MO-3-1501-228 C

3/4 3-1599-2A C

DRAIN 3-1599-28 C

360 X-310A 509-0 118 14 MO-3-1501-20A C

LPCI TEST LINE MO-3-1501-38A C

MO-3-1501-87A C

TEST CONN X-3108 238 H0-3-1501-208 C

M0-3-1501-388 C

MO-3-1501-87B C

TEST CONN 360 X-311A 509-0 120 6

M0-3-1501-18A C

LPCI TORUS SPRAY MO-3-1501-19A C

X-311B 240 MO-3-1501-188 C

M0-3-1501-19B C

360 X-150A 547-6 220 10 M0-3-1501-27B C

LPCI DW SPRAY MO-3-1501-288 C

3-1501-30B C

3-1501-298 C

X-145 M0-3-1501-27A C

MO-3-1501-28A C

3-1501-30A C

TEST CONN 3-1501-29A C

360 24 MO-3-1501-5A 0

MO-3-1501-5B 0

MO-3-1501-SC 0

MO-3-1501-SD 0

14 3-1501-31A C

14 3-1501-31B C

14" 3-1501-31C C

3-1501-310 C

345 X-105A 517-6 5

20" A0-3-203-1A C

PRIMARY STEAM A0-3-203-2A C

APPROVED 36 of 77 FEB 16 '83 D. O. S. R.

~

DTS 1500-7 Revision 5 l

UNIT 3 VALVE LINEUP (Cont'd.)

PENT L9 CATION LINE DESIRED NORMAL P&ID NO.

ELE'f. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 345 X-105A 517-6 5

3/4" 3-220-7A C

GLAND SEAL LEAK-OFF 3-220-8A C

GLAND SEAL LEAK-OFF 3-220-9A C

VLV BODY DRAIN 3-220-10A C

VLV BODY DRAIN C

2 HSL TEST CONN 0/W Cooler Damper Control N2 Supply C

Inst. Air Supply C

Air Supply at Hdr C

Air Supply Drain C

345 X-105B 517-6 10 20" A0-3-203-1B C

PRIMARY STEAM A0-3-203-2B C

3/4" 3-220-7B C

GLAND SEAL LEAK-0FF 3-220-88 C

GLAND SEAL LEAK-0FF 3-220-98 C

VLV BODY DRAIN 3-220-108 C

C 2 MSL TEST CONN 345 X-105C 517-6 350 20 A0-3-203-1C C

PRIMARY STEAM A0-3-203-2C C

3/4" 3-220-7C C

GLAND SEAL LEAK-OFF 3-220-8C C

GLAND SEAL LEAK-OFF 3-220-9C C

VLY BODY ORAIN) 3-220-10C C

VLV BODY DRAIN)

C 2 MSL TEST CONN) 345 X-105D 517-6 355 20" A0-3-203-1D C

PRIMARY STEAM A0-3-203-20 C

3/4" 3-220-70 C

GLAND SEAL LEAK-OFF 3-220-80 C

GLAND SEAL LEAK-OFF 3-220-90 C

VLV BODY DRAIN 3-220-10D C

C (2 MSL TEST CONN) 345 X-106 51; 0 0

2" MO-3-220-1 C

MSL DRAIN MO-3-220-2 C

M0-3-220-3 0

M0-3-220-4 C

3/4" 3-220-5 C

(TEST COEi) 3-220-6 C

2" MO-3-220-90A 0

M0-3-220-908 0

MO-3-220-90C 0

MO-3-220-900 0

APPROVED 37 of 77 fB 16 '83 D.O. S. R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINE UP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 345 X-106 515-0 0

2" 3-3025-500 0

(MSL DRAIN H0SE CONN) 3-3025-501 0

345 X-1358 513-9 275 3/4" 3-220-11A 0

MSL FLOW INSTR X-135C 3-220-12A 0

X-135E 3-220-11B 0

X-135F 3-220-12S 0

X-1298 3-220-11C 0

X-129C 3-220-12C 0

X-129E 3-220-110 0

X-129F 3-220-120 0

356 X-126 513-0 332 18" A0-3-1601-21 C

N PURre LINE a

A0-3-1601-22 C

3-1601-504 C

TEST CONN C

D/W TORUS VENT 4"

A0-3-1601-55 C

18" A0-3-1601-56 C

3" 3-8502-500 C

BYPASS VLV 1h" M0-3-1601-57 C

N MAKE UP A0-3-1601-58 C

N* MAKE UP A0-3-1601-59 C

3-1601-500A C

TEST CONN. BY 20A 356 X-304 509-0 270 18" A0-3-1601-20A C

TORUS VACUUM RELIEF A0-3-1601-208 C

(NOTE: FAIL OPEN) 3-1601-5008 C

(TEST CONN.10) 356 X125 572-0 145 18" A0-3-1601-23 C

DRYWELL VENT A0-3-1601-24 C

-(TO EXHAUST FANS) 2" A0-3-1601-62 C

BYPASS VENT RELIEF 6"

A0-3-1601-63 C

TO STBY GAS 3/4" C

TEST CONN EL 570' 356 X-318 509 95 18" A0-3-1601-60 C

TORUS VENT 2"

A0-3-1601-61 C

BYPASS VENT RELIEF 3/4" 3-1601-52 C

(TEST CONN EL 510') NEAR and 53 C

1601-60 and 61 3-1601-527 C

TEST CONN NEAR N MAKE UP 2

356 X-309A 498-7 155 1/2" FCV-3-8501-1A C

TORUS SAMPLE FCV-3-C 31-1B C

C

' 356 X-204 532-6 190 1

FCi-3-8501-3A C

SAMPLE RETURN FCV-3-8501-3B C

C APPROVEO 38 of 77 IO 16 '83 D.O. S. R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Co-t'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 356 X-143 547-6 120 1/2" FCV-3-8501-5A C

DRYWELL SAMPLE FCV-3-8501-5B C

FCV-3-9205A C

FCV-3-9205B C

FCV-3-9206A C

FCV-3-9206B C

3-8507-500 C

3-8507-501 C

3-8507-502 C

3-8507-503 C

3-8507-504 C

3-8507-505 C

3-8507-506 C

3-8507-507 C

3-8507-508 C

3-8507-509 C

3-8507-510 C

3-8507-511 C

3-8507-512 C

3-8507-513 C

3-8507-514 C

3-8507-515 C

3-8507-516 C

3-8507-517 C

3-8507-518 C

3-8507-519 C

3-8507-520 C

5-8507-52i C

3-8507-522 C

3-8507-523 C

367 X-136A-E 517-6 90 3/8" A Tip Ball Viv C

B Tip Ball Viv C

C Tip Ball Viv C

D Tip Ball Viv C

E Tip Ball Viv C

Tip Power Bkr #1 Racked Open Tip Power Bkr #2 Racked Open 357 X-147 564-0 29 5 2"

3-205-2-3 0

Rx HEAD COOLING MO-3-205-2-4 C

3/4" 3-205-2-1 0

DRAIN 3-205-2-2 0

DRAIN 3-205-2-5 C

TEST CONN.

3-220-48 0

Rx HEAD VENT 3-220-49 0

357 X-133A 563-0 70 1"

3-220-53 0

Rx VESSEL INSTR APPROVED 39 of 77 FG 16 '83 D.O. S. R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 357 X-1330 560-0 70 1"

3-263-2-10 0

Rx Vessel Instr.

X-1348 565-0 70 1"

3-263-2-123 0

X-134C 1"

3-263-2-148 0

X-1338 564-0 70 1"

3-263-2-12A 0

X-133C 1"

3-263-2-14A 0

X-133E 1"

3-263-2-16A 0

X-133F 1"

3-263-2-1BA 0

3-263-41A 0

X-134E 1"

3-263-2-16B 0

0 X-134F 1"

3-263-2-188 0

3-263-41B 0

X-142A 540-0 75 1"

3-263-2-21A 0

3-263-2-218 0

3-263-2-22A 0

3-263-2-228 0

3-263-2-308 0

3-263-2-30C 0

3-263-2-300 0

3-263-2-30E O

3-263-2-30G 0

3-263-2-30H 0

3-263-2-30J 0

3-263-2-30K 0

X-1428 245 1"

3-263-2-21C 0

3-263-2-210 0

3-263-2-22C 0

3-263-2-22D 0

3-263-2-30M 0

3-263-2-30N 0

3-263-2-30P 0

3-263-2-30R 0

3-263-2-30T 0

3-263-2-300 0

3-263-2-30V 0

3-263-2-30W 0

357 X-141A 541-0 145 1"

3-220-66A 0

'0/W 0 Anal Cab BRK$#1 RACKED OPEN

  1. 2 RACKED OPEN
  1. 3 RACKED OPEN
  1. 4 RACKED OPEN 3-220-668 0

3-220-66C 0

3-220-66D 0

X-151 530-0 205 1"

3-220-66E O

APPROVED 40 of 77 D. O. S. R.

DTS 1500-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZ1 SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 357 X-151 530-0 205 1"

3-220-66F 0

3-220-66G 0

3-220-66H 0

X-1308 510-0 90 1"

3-220-15A 0

X-130C 1"

2-220-16A 0

X-131B 270 1"

3-220-158 0

X-131C 1"

3-220-16B 0

3-262-2-4A 0

X-130A 1"

3-252-2-3A 0

X-1314 1"

3-252-2-3B 0

X-13uE 1"

3-220-13A 0

X-130F 1"

3-220-14A 0

X-131D 1"

3-262-2-48 0

3-263-2-24 0

3-263-2-26 0

3-263-2-32 0

X-131E 1"

3-220-13B 0

X-131F 1"

3-220-148 0

357 X-122 548-8 265 3.4" A0-3-220-44 C

Rx WATER SAMPLE A0-3-220-45 C

3-220-42 C

TEST CONNECTION 3-220-43 C

358 X-149A 564-9 20 10" 3-1402-6A 0

CORE SFRAY MO-3-1402-25A C

3/4" 3-1402-32A C

TEST CONN 3-1402-33A C

16 MO-3-1402-3A 0

12 3-1402-2A C

3-1402-46A C

3-1402-35A C

358 X-1498 564-9 155 10" 3-1402-6B 0

CORE SPRAY MO-3-1402-25B C

3/4" 3-1402-328 C

TEST CONN 3-1402-338 C

16 MO-3-1402-38 0

3-1402-28 C

358 X-310A 509-0 118 8"

MO-3-1402-4A C

CORE SPRAY TEST LINE X-310B 2?8 8"

MO-3-1402-48 C

3-1402-468 C

3-1402-35B C

359 X-108A 14" MO-3-1301-1 0

MO-3-1301-2 0

3/4" 3-1301-34 C

(TEST CONN)

APPROVED !

41 of 77 FEB16'83 A0.s.R.

OTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 359 X-108A 3/4" 3-1301-35 C

(TEST CONN)

C 2 VLVS GLAND SEAL OFF 1"

3-1301-21 0

3-1301-22 0

X-1320 3-1301-27 0

X-132A 3-1301-28 0

X-10SA 3/4" A0-3-1301-17 C

A0-3-1301-20 C

3-1301-602 C

TEST CONN 3-1301-603 C

3-1301-14 C

(VENT) 3-1301-15 C

3-1301-501 C

3-1301-500 C

359 X-109A 547-10 178 12" MO-3-1301-3 C

ISOLATION COND MO-3-1301-4 C

3/4" 3-1301-32 C

(TEST CONN) 3-1301-33 C

3-1301-18 C

(0 RAIN) 3-1301-19 C

2 VLVS RWCU HDR DRAIN C

2 VLVS RWCU HDR DRAIN 361 X-113 547-10 300 10*

MO-3-1201-1 C

Rx CLEANUP MO-3-1201-2 C

MO-3-1201-3 C

3/4" 3-1201-31 C

3-1201-32 C

3-1299-13 C

3-1299-7 C

DW TEST CONN 3-1299-8 C

363 X-111A 530-8 25 16" MO-3-1001-1A C

SHUT DOWN COOLING 3/4" 3-1001-45A C

DRAIN 3-1001-46A C

3-1001-47A C

DRAIN 3-1001-48A C

14" MO-3-1001-2A C

M0-3-1001-23 C

3/4" 3-1001-92A C

(DRAIN) 3-1001-928 C

DRAIN 3-1001-88A C

GLAND SEAL LEAK OFF 363 X-111B 530-7 70 16" M0-3-1001-18 C

SHUTDOWN COOLING 3/4" 3-1001-45B C

DRAIN APPROVED 42 of 77 FEB 16 '83 D. O. S. R.

l 1

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd,.)

PENT LOCATION LINE DESIRED NORMAL P&IO NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 363 X-111B 530-7 70 3/4" 3-1001-468 C

DRAIN 3-1001-478 C

3-1001-488 C

14" M0-3-1001-2C C

3/4" 3-1001-92C C

DRAIN 3-1001-888 C

GLAND SEAL LEAK OFF 363 X-116A 513-9 83 14" M0-3-1001-5A C

SHUT DOWN COOLING 3/4" 3-1001-10A C

GLAND SEAL LEAK-OFF 3-1001-14A C

3-1001-28A C

3-1001-29A C

363 X-1168 513-9 263 14" M0-3-1001-5B C

SHUTDOWN COOLING 3/4" 3-1001-10B C

GLAND SEAL LEAK-OFF 3-1001-14B C

3-1001-288 C

3-1001-298 C

364 X-138 581-0 340 14" 3-1101-1 0

SBLC 3/4" 3-1199-005 C

2 Vivs VENT: IN OW

-006 C

TEST CONN 3-1199-9 C

2 Vivs TEST CONN:

IN DW

-10 C

2 V1vs TEST CONN:

IN DW

-003, 004 C

2 Vivs TEST CONN: OUT DW

-3, 4 C

2 Vivs TEST CONN: OUT DW 365 X-1098 547 185 4"

3-301-500 C

CRD RETURN 3-301-501 C

CRD RETU?w 3-301-93 C

CRD RETUkn 3-301-96 C

CR0 RETURN 3-301-97 C

CR0 RETURN 367 X-121 527-6 283 1"

3-4741-20B C

DW PNEUMATIC SYSTEM 3-1601-48 0

2" A0-3-4722 C

k" Top Test Conn.

C 3-4741-20C 0

(VENT) R9 MOVE CAP 367 X-1390 536-6 280 1"

A0-3-4720 C

DW PNEUMATIC SYSTEM Test Conn.

C A0-3-4721 C

3-4771-500 0

VENT PATH 3-4771-501 0

368 X-120 527-6 28 0 1"

3-4640-5G0 C

SERVICE AIR l

0 VENT VALVE OFF 0F LINE l

4"

'^~#~

APPROVED FG 1613 43 f 77 D.O.S.R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 4" Service Air Stop Outside Sludge Tank Rm Top Valve C

0 VENT SERVICE ON 517' LEVEL WEST Service Air Top just inside the Sludge Tank Rm.

0 C

VALVE ON LINE 3-4609-A' 369 X-118 512-3 45 3"

A0-3-2001-105 C

DW EQUIP DRAIN A0-3-2001-106 C

X-117 512-3 185 3"

A0-3-2001-5 C

DW FLOOR DRAIN A0-3-2001-6 C

A0-3-2001-3 0

374 X-128 513-9 97 10" MO-3-2301-3 C

HPCI MO-3-2301-4 C

M0-3-2301-5 C

MO-3-2301-6 0

3/4" 3-2301-15 C

TEST CONN.

3-2301-17 C

MO-3-2301-35 C

16" M0-3-2301-36 C

3/4" 3-2301-93 C

DRAIN 3-2301-94 C

374 1"

S0-3-2301-31 0

S0-3-2301-29 C

S0-3-2301-30 C

3-2301-43 C

TEST CONN.

3-2301-44 C

374 X-132C 542-6 160 3/4" 3-2301-24 0

HPCI INSTR X-132B 3-2301-25 0

X-317A 509-10 190 3/4" 3-2301-41A C

HPCI (TEST CONN) 3-2301-42A C

S0-3-2301-28 C

497-0 200 3/4" 3-2301-41B C

HPCI (TEST CONN) 3-2301-423 C

1" S0-3-2301-32 C

3-2301-50 0

UNMARKED BYPASS VALVE 3-2301-74 0

AROUND 3-2301-33 AND MO-3-2301-14 C

3-2301-47 BKR for 2301-14 RACKED OPEN 707 125 572 215 3/4" 3-2599-15A C

ACAD Sh 2 3-2599-15B C

ACAD of 2 3-2599-16A C

ACAD 3-2599-16B C

ACAD 1"

A0-3-2599-4A C

ACAD FEB 16'83 44 of 77 D.O.S.R.

DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)

PENT LOCATION LINE DESIRED NORMAL P&ID NO.

ELEV. AZI.

SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 707 125 572 215 1"

A0-3-2599-5A C

ACAD Sh 2 A0-3-2599-48 C

ACAD of 2 A0-3-2599-5B C

ACAD 146 541 105 3-2599-25A 0

ACAD A0-3-2599-2A C

ACAD 140B 530 310 3/4" 3-2599-11A C

ACAD 3-2599-12A C

ACAD 316A 504 60 1"

A0-3-2599-3A C

ACAD 3/4" 3-2599-13A C

ACAD 3-2599-14A C

ACAD 127 531 245 l'

3-2599-25B 0

ACAD 3-2599-21 0

RECEIVER DRAIN VALVE 127 531 245 A0-3-2599-2B C

ACAD 3/4" 3-2599-11B C

ACAD 3-2599-123 C

ACAD 3168 504 280 1"

A0-3-2599-3B C

ACAD 3/4" 3-2599-13B C

ACAD 3-2599-14B C

ACAD 146 541 105 1/2" S0-3-2499-2A C

CAM S0-3-2499-1A C

CAM 1/2" 3-2499-7A C

CAM 1/2" 3-2499-8A C

CAM 316A Torus 65* 1/2" S0-3-2499-4A C

CAM S0-3-2499-3A C

CAM 1/2" 3-2499-10A C

CAM 1/2" 3-2499-9A C

CAM 127 532 245 1/2" S0-3-2499-2B C

CAM S0-3-2499-1B C

CAM 1/2" 3-2499-7B C

CAM 1/2" 3-2499-8B C

CAM 3168 Torus 305' 1/2" S0-3-2499-48 C

CAM S0-3-2499-38 C

CAM 1/2" 3-2499-108 C

CAM 1/2" 3-2499-98 C

CAM APPROVED 45 of 77 D.O.S.R.

DTS 1600-7 Revision 5 INSTRUMENT MAINTENANCE DEPARTMENT CHECKLIST 4 A.

Pretest Requirements 1.

Obtain and supply to the responsible Tech Staff Engineer a cali-bration curve for the read-out of sensor LI-2(3)-263-101.

2.

Take the "A" Pumpback air compressor OUT-OF-SERVICE and then l

disconnect and vent the low suction pressurc switch trip sensing line to atmosphere.

s) l Verified 3.

Install and connect all instrumentation (includes both plumbing and electrical connections) both inside and outside the containment.

Verified 4.

Install the cable from the LT 2(3)-263-61 to I.L.R.T. console channel 5 (for Rx. water level).

Verified 5.

Remove existing temperature sensor from the 2(3)-1045 A & B well then insert volumetric RTD's in A & B loop (SOC pump room).

Verified B.

Test Requirements 1.

During the full duration of the test, no surveillances shall be conducted that have the potential of causing a scram.

Verified C.

Post Test Requirements 1.

Disconnect and remove all ILRT temporary instrumentation.

Verified 2.

Connect the "A" Pumpback air compressor low suction pressure switch trip sensing line and clear the system outage.

Verified APPROVED FEB 16'83 46 of 77 0.0.S.R.

DTS 1600-7 Revision 5 3.

Calibrate the following pressure sensors after completion of the test.

PS-3-1621A PS-3-1632A PS-1501-62A PS-3-1628A PS-3-16218 PS-3-16328 PS-1501-628 PS-3-16288 PS-3-1621C PS-3-1632C PS-1501-62C PS-3-1629A PS-3-16210 PS-3-16320 PS-1501-620 PS-3-16298 Verified 4.

Remove the cable fram the LT 2(3)-263-61.

Verified 5.

Remove the RTD's from 2(3)-1045 A & B and reinstall the existing temperature sensors.

Verified 1

APPROVED FB 16'83 47 of 77 D.O.S.R.

r-DTS 1600-7 Revision 5 TECHNICAL STAFF CHECKLIST 5 A.

Pretest Requirements 1.

Arrange for the calibration of the instrumentation to be used.

Verified 2.

Make a survey of the primary containment for the purpose of establishing any tendencies for regional variations in temp-eratu re. This survey will be u ed in determining where to place the temperature sensing devices.

Verified NOTE Where testing experience with a given containment structure has previously established appropriate locations for temperature sensors, temperature surveys may be eliminated.

3.

At the same time as the temperature survey, conduct a survey for the purpose of detemining the placement of the humidity indicators so that a representative sampling of the primary containment air can be made.

Verified NOTE As in the case of the temperature survey, this humidt ty survey may be eliminated for a containment structure which has known and char-acteristic humidity patterns.

4.

Determine the placement of all temperature and humidity sensing devices from the surveys in steps 2 and 3 above.

Verified 5.

Obtain the instrument accuracies for all instruments and read-out devices to be used in the ILRT.

Perfonn an error analysis to verify that the accuracy of the collected data is consistent with the magnitude of the specified leakage rate. This analysis must be done prior to the placement of any instrumentation in the primary containment for the test. (See Appendix A, attached, for a sample calculation.)

APPROVED FEB 16'83 48 of 77 D.O.S.R.

DTS 1600-7 Revision 5 INTERPRETATION Specifically, the combined instr-ument repeatability error should be less than 2ET, of La, the maximum allowable leak rate.

Verified 6.

Arrange for the availability of the air compressors for use in pressurizing the containment.

Verified 7.

Examine LLRT results for all tests and verify that all Tech-nical Specification limits have been met prior to the start of the ILRT. Also, obtain the total calculated leakage fran the primary containment penetrations both prior to and after repairs (in the case of double gasketed seals, before and after opening the seal). This information will be required when the results of the ILRT are analyzed.

Verified 8.

Arrange with the Instrument Mechar.ics for placement of the calibrated instrumentation in the primary containment and its connection to read-out devices outside the primary containment.

Verify the location and operability status of the instrumentation.

Verified 9.

Verify the availability of instrumentation for the recording of ambient changes in the reactor building. These devices need only be of such accuracy that they will indicate gross barometric variations for correlation to test results.

Verified 10.

Determine the volume of the primary containment associated with each temperature and humidity sensing device. This information will be used during the test for volume weighting the data.

Verified 11.

Ensure that the air compressors, piping, manifolds and connections to the penetrations are installed by the Main-tenance Department as required. Also verify proper operation of the compressors.

Verified APPROVED 12.

Conduct a thorough examination of the drywell and pressure FEB 16 '8' 49 of 77 D.O.S. R.

1

DTS 1600-7 Revision 5 suppression containment to remove any pressurized vessels, gas pressure cylinders, sealed or semi-sealed containers, and anything which, in the judgement of the Test Director, could be damaged by the pressure test atmosphere or have a direct bearing on the results of the leakage rate measurement.

%erified 13.

Verify valve line-up of Operating Department Checklist prior to starting the test.

Verified 14.

Verify that the personnel air lock is closed and locked.

Verified 15.

Direct the Operations Department in the pressurizing of the primary containment.

Verified 16.

Initiate a dated log of events and pertinent observations.

This log must be maintained for the duration of the ILRT.

Verified 17.

Prepare graph paper for the plotting of the appropriate data.

Verified 18.

Ensure that the following penetrations are closed and have been local leak rate tested.

Equipment Hatch CRD Removal Hatch Torus Access Hatches Drywell Head Verified 19.

Fill out Figure 2 by specifying the number and location of each RTD in within the subvolumes indicated inside of the containment.

Verified 20.

Record sump levels in the drywell equipment drain sump and the drywell floor drain sump.

Equip Sump Level inches APPROVED Floor Dr Sump Level inches FEB16*B3 D.O.S.R.

50 or 77 l

I

DTS 1600-7 Revision 5 l

S.

Post Test Requirements 1.

Verify that all temporary instrumentation is removed.

Verified 2.

Verify that the torus access hatch that was opened for the removal of instruments is again local leak rate tested upon final closure.

Verified 3.

Record pump levels in the drywell equipment drain sump and the drywell floor drain sump.

Equip Sump Level Floor Dr Sump Level 4.

Verify that following pressure switches have been calibrated after completion of the test PS-3-1621A PS-3-1621B PS-3-1621C PS-3-16210 PS-3-1632A PS-3-16328 PS-3-1632C PS-3-1632D PS-3-1501-62A PS-3-1501-623 PS-3-1501-62C FS-3-1501-620 PS-3-1628A PS-3-16288 PS-3-1629A PS-3-1629B Verified RADIATION PROTECTION CHECKLIST 6 1.

Prior to.any venting of the primary containment, an air sample must be taken for analysis.

Verified APPROVED 51 of 77 D.O.S.R.

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u) m O

a5 DATA SHEET 2 DATE

?

w IT1 DATA TABULATION O

UNIT AVERAGE AMBIENT M8IENT REACTOR REACTOR TORUS AMBIENT AM8IENT RELATIVE RELATIVE WATER WATER WATER SUPERIMPOSED HWR TEMPERATURE PRESSURE HUMIDITY HUMIDITY TEMPERATURE LEVEL (In LEVEL (In LEAK RATE

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DTS 1600-7 Revision 5 APPENDIX A A.

INSTRUMENT ACCURACY ERROR ANALYSJS Per Topical Report BN-TOP-1 the measured total time leak rate (M) in weight percent per day is computed using the Absolute Method by the fomula H=(100)f I "

1-nP1_

where:

F = P -PV = total containment atmosphere absolute pressure, g

1 1

in psia, at the start of test, corrected for water vapor pressure.

Fe P -PV = total containment atmosphere absolute pressure, 2

in psia, at data point n after start of the test, corrected for water vapor pressure.

T,T containment mean atmospheric temperature in or

=

1 n

at the start and at data point n, respectively.

H test interval in hours between time 1 and time n.

=

R gas ccnstant.

=

The change or uncertainty interval in M due to uncertainties in the measured variables is given by:

M

= 2400 dM OP dM OP 2

+

I H

dP dP 2

1 (2)

O S

OT dM T

dM 1

+

2 p1 2

where S is the standard error for each variable. This fomula assumes that all errors are systematic rather than radom in character.

Even though the formula is deteministic it does, however, allow assessment of figure of merit for various equip-ment to be used in the measuring system without the need for assembling and calibrating the system as an entity.

APPROVED FEB 16'83 59 of n D.O.S.R.

DTS 1600-7 Revision 5 The error in M after differentiating is:

T e

2 7

2400 y

p 21

'E e

1 g

=H p7 T

2 1 2 F

T i

2 e

27 T

+

+

T I

I2 I2 whers:

e

=3 I

1 e

=$

P 2

2

'T

  • 'T " 'T 1

2 For the purpose of developing a finite number for e using equation g

(3), it is necessary to assume certain containment conditions made.

1.

For purposes of comparison to other tests H = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Containment leak rate is essentially zero, that is:

T

=T

=i where i is the average volu:ae weighted primary g

7-containment air temperature (*R) during the test; P

=P where P is the total containment atmospheric 1

2 prassure (psia);

PYg = PV2 where PV is the partial pressure of water vapor in the primary containment; Equation (3) becomes:

'M 2 00 2(P ) +2(i )

=

APPROVED

~

FEB 16'83 60 of 77 0.0.S.R.

s CTS 1600-7 Revision 5 where:

e

= the error in pressure which accounts for the P

error in the total pressure measurement system; both total absolute pressure and water vapor pressure.

b (ep)

(ep) e

=

+

p e

= inst. accuracy error / /no. inst. = error in p

T total absolute pressure in psia.

e

= inst. accuracy error / vno inst. = error in p

V water vapor pressure (dewpoint) indicator in psia at 70*F.

e

= inst. accuracy error / Vno. inst. = error in T

tenperature

'R.

4 APPROVED F516 '83

)

61 of 77 D.O.S.R.

OTS 1600-7 Revision 5 APPENDIX B A.

INSTRUMENT ACCURACY ERROR ANALYSIS Per ANSI N45.4-1972, the computation of the leak rate is given by the equation.

L(%)=(f)'100)(N' { U) (1 -

)

where L = primary containment leak rate (wt"./ day) l H = time interval between data sets #1 & #2 (hours)

W = weight of the contained dry air mass at 1

test data set #1 (lbs)

W = weight of primary containment temperature 2

i at test data set #2 (lbs)

T = volume weighed primary containment tem-y perature at test data set #1

(*R)

T = v lume weighed primary containment tem-2 perature at test data set #2

(*R)

P = dry air absolute pressure at test data g

set #1 (psia)

P = dry air absolute pressure at test data 2

set #2 (psia)

The standard variation on L due to the uncertainties in the mea-sured variables is,given by:

S(L) = 2400 g(

3(p ))2, (

g(p )) +(

S(T)) +(hS(T)) 3 g

2 g

2 1

2 1

2 substituting H = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 8,

al T.

-1 8P " ~R ' T g

=.

e-l

~

assuming P = P "If and T = T = T I

g 2

g 2

where 7 = average absolute dry air pressure (psia)

T = average volume weighed primary containment absolute temperature (*R)

Therefore, APPROVED 62 of 77 FB 16'83 D.O. S. R.

DTS 1600'-7 Revision 5 S(L) = 100[2(0 I )* + 2(0 I)*]h 7

Y 1.

Calculation of S(T)

T=

VF ) (Tave,3) 3 where VF3 = the volume weighing factors NVOL = the number of containment subvolumes Tave,d = subvolumethe average absolute temperatuare in the jth N

~

Tave, = IdE Nd

,=1 where T1.j = the absolute temperatuare of the ig RTD in the jg NJ = number of RTD's in the jth subvolume Now, S(T) is calculated from NVOL S(T) =

S(Tave,j) 8 Tav,j where dTay,j " #d 6(Tave,j) = RE accuracy (N )4 Therefore, i

NVOL S(f) =

(Vfj) (R acy) a 2.

Calculation of S(7)

(P ) ]b S(P) = [S(P )

+

T y

l where PT = total absolute primary containment pressure APPROVED p

y, c,,on,,tainment,,3,,,,,,,, of,,,,, y,,,, i n en,,,,,,,,

FB 1613 63 of 77 D.O.S. R.

--.n.-

,.-,.--m

DTS 1600-7 Revision 5 accuracy substituting S(PT) =

(# of PPG's)

OL g(py), I

[yp ) (dewcell accuracy) j=1 (Nj) where PPG = precision pressure gage NJ = number of dewcells in the j h subvoluu Therefore; 2

6(h = [( j o

,)

,(

(yyj) (dewcell a uracy))2) ac a

a 3.

Detemine the appropriate variable quantities and perfom the aliove analysis twice - once for the system accuracy and once for the system repeatability.

1 APPROVED 64 of 77 D. O. S. R.

DTS 1600-7 Revision 5 APPENDIX C CALCULATIONS PERFORMED Data collected from pressure sensors, de.wcells, and RTD's located in the containment are processed using the following calculations for containme".t temperature and dry air pressure.

A.

'verage Subvolume Temperature and Dewpoint.

Tj = I(all RTD's in JSsubvolume)

.F (1)

Number of RTEPs in the ja subvoluri;e D.P.j = I(all dewcell in JS subvolues)

.F (2)

Number of dewcells in ja subvolume where Tj = average temperature of the jp subvolume D.P.j = average dewpoint of the J.th subvolume h

NOTE l

By definition D.P.j i Tj)

~

B.

Primary Containment Temperature and Dry Air Pressure NVOL If Tj = undefined, then T=

I (VFj) (Tj) *F (3)

Tj = T (j + 1) for liji(NVOL-2) j=1 Tj = T (j - 1) for j = NVOL-1 Tj = estimate, for j = NVOL NVOL If D.P.j = undefined, then D.P. =

I (VFj)(D.P.j) *F (4)

D.P.j = 0.P. (j + 1) for 1sjs(NVOL-2) j=1 0.P.j = 0 P. (j - 1) for j = NOVL-1 0.P.j = estimate, for j = NVOL D. P. ( *K) = 273.16 + E*' *

)

X = 647.27 - D.P. (*K) 8 EXPON = X(A + ZX + CX3)

A = 3.2437814 (D.P. ( "K))( 1+DX)

Z = 5.86826.10

py, (218.167) (14.696) PSI C = 1.702379.10-8 e(EXPON in 10)

D = 2.1878462.10.s I(All absolute pressure gauges) p, Number of absolute pressure gauges-PV Psia (5) y where: NVOL = number of primary containment subvolumes VFj = volume weighing factor of the jg subvolume T = volume weighed containment -temperature D.P. = volume weighed containment dewpoent X,A,Z,C,D,EXPON = dewpoint to vapor pressure conversion APPROVED constants a coefficients RB 16'80 65 of 77 D.O.S.R.

DTS 1600-7 Revision ~5 Py = volume weighed containment vapor pressure P = contained dry air absolute pressure NOTE The subvolume numbering sequence is from the warmest to the coolest subvolume. (Assuming top to bot-tam due to stratification.)

A APPROVED RB 16'83 66 of 77 D.O. S. R.

DTS 1600-7

' Revision 5 APPENDIX D CALCULATIONS PERFORMED ~0R" IPCLRT DATA FOR TEST DURATION AT LEAST 12 HOURS Data collected from pressure sensors, dew cells, and RTD's located in the containment are processed using the following equations. $cre data needs to be analyzed using equations in Appendix C prior to use.

Those equations are referenced by equation number. The primary reference for these calculations is the Topical Report BN-TOP-1 Revision 1.

A.

MEASURED LEAK RATE (Total Time)

From BN-TOP-1 Rev.1, Section 4.5 the following equation is given for the measured leak rate using the tota! time procedure:

$ = 2400 ( 1 _ T%)

(% erday)

M g

io where M measured leak rate in weight % per day for

=

y th the i data point.

H time interval, in hours, between measurements.

=

T,, Tj mean absolute temperature, 'R, of the containment

=

atmosphere at the beginning and the end of test interval (H) respectively.

P,, P$

mean total absolute pressure, psia, of the

=

containment atmosphere at the beginning and end of the test interval (H) respectively.

Using the following relationship derived in ANSI N45.4 - 1972 Appendix B given below:

NoNi T, 79

,1, T P, N

g o

where W,, W9 = dry air mass of the containment at the beginning of the and data point i, respectively.

And substituting in the calculation of the containment dry air mass that corrects for a change in Reactor Water level given in Appendix C eq. 6 gives the following expression for the measured leakage:

T, 7 (volume - (LEVEli - 50)(28.635)))

M 2400 1

[3, g

T E, (volume - (LEVEL, - 50)(28.635))

g APPROVED where LEVEL,, LEVEL, = reactor water level in inches at beginning of the test and the data point 1, respectively.

FEB 16'03 37 of 77 D.O.S. R.

DTS 1600-7 Revision 5 j

B.

CALCULATED LEAK 2 ATE The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of v:3sured da ta. The criterion for the best fitting line to a set of data points is that the sum of the squares of the deviations of the observed points from the line must be a minimum. When this critarion is met, a unique best fitting line is obtained based on all of the data points in the ILRT. The value of the leak rate based on the regression is called the statistically average leak rate.

Since it is assumed tnat the leak rate is constant during the testing period; a plot of the measured contained dry air mass versus time would ideally yield a straight line with a negative slope (assuming 6 non-zero leak rate). Obviously, sampling techniques and test conditions are not perfect and consequently the measured values will de/iate from the ideal straight line situation.

Based on this statistical process, the calculated leak rate is obtained from the equation:

L9=Aj+89 g

xt where tg = time in hours since the beginning of the th test to the i data set point.

The values of the constants A and B such that the regression line is best fitting to the ILRT data are B = I" II III - III IIII III i

[n I( t,)2 - (It )2J y

IMi BFi A=j n

In order to reduce the round-off error in the above calculatons, the equations are rearranged such that:

nyt M,, (g,)g'4 )

t 9

9 B=j nI(t )2 (It )2 9

9 3, (I i)(I,2) _ (y,)(7,M,)

M t

t t

i nit,2 - (It )2 j

9 APPROVED 68 of 77 FEB 16'83 l

D.O.S.R.

DTS 1600-7 Revision'5 C.

95% CONFIDENCE LIMITS To detemine the value of the confidence limits the following statistical infomation is required; the variance, standard deviation, and students' T-distribution.

3:. SSO n-2 where SSQ =

(M9 - L )2 g

S2 variance

=

S standard deviation based (n-2) degrees of

=

freedom.

The standard deviation has more practical significance since computing the standard deviation returns the measure of variability to the original units of measurement. Addi tionally, it can be showr, that given a nomal distribution of measurements, approximately 95%

of the measurements will fall within two standard deviations of the mean.

The number of standard deviations either side of the regression line which establish a 95% confidence interval are more accurately determined using a statistical table called a " Table of Percentage Points of the T-Distribution" and provide increased confidence in outcomes for small and large sample sizes.

The Table of T-Cistributions has been fomulized for use by the computer program as follows:

TD = 1.95996 + 2.37226, 2.8225 (n-2)

(n-2)2 where TD = value of T-Distribution for the 95% confidence limit and (n-2) degrees of freedom.

th n = number of data points including the i data point.

The application of the additional factor to the variance fomula yields:

[ 1 + 1 + (t D ~ *)

a = S2 2

]

n I(tg - t)*

[ 1 + 1 + bD - I)* ] h g.S n

I(tg - t)2 APPROVED FEB 16'83 69 of 77 D.O.S.R.

DTS 1600-7 Revision-5 where t = tima after start of test g

i. It, n

UCL = Lg + TD x a APPROVED FB 16'83 7g of 7 D.O.S.R.

DTS 1600-7 Revision S APPENDIX E CALCULATIONS PERFORMED FOR IPCLRT (IATA FOR TEST DURATION AT LEAST 24 HOURS i

Data collected frum pressure sensors, dew cells, and RTD's located in the containment are processed using the following equations. Some data needs to be analyzed using aquations in Appendix C prior to use these equations.

A.

Contained Dry Air Mass.

W = (28.97)(144)(P)[(volume) - (LEVEL-50)(28.635)] lbs.

1545.33 (T + 459.69)

LEVEL = reactor water level in inches from instrument zero (28.635 ft/in)

Volume = primary containment volume (ft) with:

Rx level 0 50.0 inches, Torus level 0 - 3.0 inches.

B.

Measured Leak Rates.

Lm(TOTAL) = N Base Ni 2400

  • i ~
  • Base W

Day Base Lm(POINT) = W -1 Ni 2400 i

t

- t -1 W

Day j

j

$_)

where, WBASE = mass of contained air at t=0 (lbs)

W9 = mass of centained air at t=1 hrs (1bs) tg = test duration at the 11h, data set (hrs) h C.

Statistical Leak Rate and Confidence Limits.

LINEAR LEAST SQUAPES FITTING OF THE IPCLRT DATA The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured data. The criterion for the best fitting line to a set of data points is that the sum of the squares of the deviations of the observed points from the line must be a minimum. When this criterion is met, a unique best fitting line is obtained based on all of the data points in the ILRT. The value of the leak rate based on the regression is called the statistically average leak rate.

Since it is assumed that the leak rate is constant during the testing period; a plot of the measured contained dry air inass versus time would ideally yield a straight line with a negative slope (assuming a non-zero leak rate). Obviously, sampling techniques and test conditions are not perfect and consequently the measured values will deviate from the ideal straight line situation.

APPROVED i

71 of 77 D.O.S. R.

~

DTS 1600-7 Revision 5 Based on this statistical process, the calculated leak rate is obtained fror,, the equation:

W = At + B

~

where W = cantained cry air mass at time t (1bs)

B = calculated contained dry air mass at time t= 0 lbs)

A = calculated leak rate lbs/hr) t = test duration hours)

Contained Dry Air Mass

(

(lbs)

N09 4

Test Duration (hrs)

The values of the constants A and B such that the regression line is best fitting to the !LRT data are g, [NI(ti) (Wi)] - [ Gti) GWi)]

[NI( ti)2 (Iti)'j g, IWi - Alti N

In order to reduce the round-off error in the above calculations, the equations are rearranged such that:

4,I :(ti-t)(Wi-Q)]

.I(ti-t)'J B=[ (ti)2)C:Wi)] - [Gti)G(ti)(Wi))]

[ G( ti)*

- (Iti)23 By definition, leakage out of the primary containment is considered positive leakage; therefore, the statistically average laat rate in weight percent per day is given by:

Ls = (-A)(2400)/B (weight %/ day)

Statistical Uncertainties APPROVED In order to calculate the 95% confidence limits of the statiscally ps16'83 D.O.S R-

DTS 1600-7 Revision 5 average leak rate, tne standard deviation of the least squaras siope and the Student's T-01stribJtion function are used as follow:

1 NI Wi)2.(Igi)z a

'*E E

  • ^

NW NHti)2 -Eti)*

UCL = l + a(TE)(2400) s B

where TE = 1.645 + 1 0 7

N = number of data sets ti = test duration at the ith data set Wi = contained dry air mass 7t the i_t_h data set h

a = standard deviation of least squares slope TE = value of the single-sided T-Distribution function with 2 degrees of freedom Ls = calculated leak rate in %/ day UCL = 95% upper confidence limit in %/ day APPROVED 73 of 77 D.O.S.R.

a

, e e

i DTS 1600-7 Revision 5 APPENDIX F IPCLRT DEFINITIONS (48 PSIG TEST PRESSURE)

Maximum Allowable Leakage Rate (La)

La = 1.6% of containment volume.per day

= (0.016)(288,966 ft3)/24 hrs.

= 192.644 ft3/hr.

48 14 696

= 192.644 SCFH

= 821.857 SCFH Maximum Allowable Operation Leakage Rate (L }

t L = 75% of Maximum Allcwable Leakage Rate t

= (0.75) (821.557) SCFH

= 616.392 SCFH Maximum Allowable Leakage for any One Main Steam Isolation Valve 11.5 SCFH 0 25 psig test pressure Maximum Allowable Leakage Rate for all testable penetrations and isolation valves except main steam isolation valves is 60 percent of L

  • t (60%) (821.857) = 493.114 SCFH Maximum Allowable Leakagt. Rate of the personnel interlock door is 3.75 percent of La.

(3.75%) (821.857) = 30.820 SCFH APPROVED l

FEB 16'83 74,, 77 D.O.S.R.

p F Y e

t e

DTS 1600-7 Revision ~5 TABLE I List of Non-Vented System SYSTEM NO.

PENETRATION NO.

LEAK RATE (SCFH) 220-57A & 220-58A X-1078 220-57A & 220-62A X-107B 220-57B & 220-588 X-107A 220-575 & 220-623 X-107A 301-95 & 301-99 X-1098 301-98 & 301-99 X-109B 1001-1A,1B,2A,2B & 2C X-111A/X-1118 1101-1 & 1101-15 X-138 1101-1 & 1101-16 X-138 1201-1, 2 & 3 X-113 1301-3 & 1301-4 X-109A 1402-4A,8A,25A & 36A X-310A 1402-24A & 25A X-1498 1402-48,88.25B & 36B X-310B 1402-248 & 258 X-149A 1501-18A & 19A X-311A 1501-188 & 19B X-311B 1501-20A & 1501-38A X-310A 1501-208 & 1501-38B X-3108 1501-22A,26A & 1001-5A X-116A 1501-25A & 1501-26A X-116A 1501-228,268 & 1001-3B X-1168 l

1501-258 4 1501-268 X-1165 1501-27A & 1501-28A X-145 1501-278 & 1501-288 X-150A 2301-45 & 2301-74 X-317 APPROVED FEB 16'83 75 cf 77 l

D.O.S.R.

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