ML20082H189
| ML20082H189 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Dresden |
| Issue date: | 03/31/1983 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20082H066 | List: |
| References | |
| FOIA-83-384 DTS-1600-7, NUDOCS 8312010048 | |
| Download: ML20082H189 (77) | |
Text
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DTS 1600-7 Revision 6 March 1983 UNIT 2/3 INTEGRATED PRIMARY CONTAItMENT
(
LEAK RATE TEST s..
A.
PURPOSE The purpose of this procedure is to detail the steps necessary 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.
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2.
10 CFR Part 50, Appendix J January 1975 - Primary Rep.ctor 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 Criteria For Integrated Leakage Rate Of Primcry Containment Structures For Nuclear Power Reactors.
5.
Sargent and Lundy drawings:
a.
B-21, 6-22, B-24, and B-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 integer.ted leak rate' test.
2.
A signed and dated events log must be initiated by the respon-sible Tech Staff Er.gineer 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.
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DTS 1600-7 o
Revision 6 NOTE i
u Local leak rate tests must be done prior to and after any repair work being done on any penetration or associated isoletion valve.
In the special case of double gas-keted seals, local leak rate tests must be done prior to openis,q the seal and after closing the saal.
5.
All pre-test checklists must be completed and returned to the responsible Tech Staff Engineer prior tc the start of the test.
l NOTE The work to be perf,,med 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 facilitate the e
execution of the ILRT.
s-6.
All 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 l
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-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.
toad 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 Dep: rtment at least two weeks l
in advance.
t APPROVED 1
M 22 '83 g,,,
D.O.S.R.
1
r DTS 1600-7 R; vision 6 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 of sensor placement within the containment and a simplified flow diagram of the ILpT computer program.
14.
Contact the American Nuclear Insurers Co. prior to perfoming the test.
D.
PRECAUTIONS 1.
Warning signs shall be posted 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 practices and rules will be strictly followed for this test.
t 3.
All requests for equipment out-of-service for repairs during the test must be evaluated with respect to the fact that the primary containment will be under approximately 48 psig.
l 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 y
reactor cavity area.
5.
If use of the shutdown cooling system is anticipated at any-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 recircul'ation pumps not running, either the recirculation pump suction valve (MO-202-4A or B) or discharge valve (MO-202-5A or B) and (MO-202-7A or B) must be closed in order to insure that flow is es-tablished through the reactor ves-sel and not through the idle pump.
APPROVED 3 # 77 NAR 22 '83 D.O.S.R.
DTS 1600-7 Revision 6 E.
LIMITATIONS AND ACTIONS C
1.
The integrated lea;: age rate test will be conducted by pressurizing the primary containment to a pressure of at least the calculated maximum peak accident pressure of 48 psig.
2.
After the preoperational leakage rate tests, a set of three type A tests shall be perfomed, 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.
The indicated leak rate shall be less than Lt (75% La).
a.
b.
The apper 95% confidence limit of the indicated leak rate, which includes appropriate consideration for ran-dom measurement errors, shall also be less than Lt (75% La).
4.
Drywell pressurization will be discontinued 'if leakage above the maximum allowable rate is obvious or the drywell pressure I
cannot be increased.
Repairs will be made and the test re-s tarted.
NOTE Before teminating the test, a leak rate must be detemined for report-ing to the NRC.
If the test is thus teminated, a Reportable Occurrence must be issued.
5.
During the period between the initiation of the con'.ainment inspection 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 completion of one Type A test and the initiation of the containment inspection for tne sub-sequent Type A test, repairs or adjustments shall be made to components whose leakage exceeds that specified in the Tech-nical Specifications as soon as practical after identification.
[
APPROVED WR 2213 4 #
D.O.S.R.
r DTS 1600-7 Revision 6 7.
If during a Type A test, including the supplemental induced
(
leakage test, potentially excessive leakage paths are iden-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 methodr,. Repairs and/or adjustments to equip-ment shall be made and the Type A test restarted. The cor-rective action and the change in leakage rate detemined fror:
the tests and overall integrated leakage determined from the local leak and Type A tests shall be included in the report submitted to the Commission.
8.
Closdre of containment isolation valves for the Type A test shall be accomplished by nomal operation and without any preliminary exercising or adjustments.
Repairs of malopera-ting o.- leaking valves shall be made as necessary.
Infor:aa-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. (Pressurizat1on and Stabilization),
i 10.
All vented systems shall be drained of water or other fluids f
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. Systams that are required to maintain the plant in a safe condition during the test shall i
be operable in their nomal mode, and need not be ventad.
Systems that are normally filled with water and operating under r.ost-accident conditions, such as the containment heat i
l removal system, need not be vented.
Refer to Table 1, list of non-vented systems.
11.
Results of the supplemental 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:
(induced phase L l(measured phase}+ L (superimposed L i calculated calculated l
1.25 La (leak rate (leak rate,
j (leak rate If results are not within 0.25 La, the reason shall be de-termined, corrective &ction taken, and a successful supple-mental test perfomed.
APPROVED u
MR 22 '83 5 f 77 D. O. S. R.
\\
r DTS 1600-7 Revision 6 12.
A general inspection of the accessible interior and exterior
(
surfaces of the primary containment structure and components shall be perfonned 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 perfonced until corrective action is taken. Such structural deterioration and corrective actions taken shall be reported as part of the test report.
13.
If the shatdown cooling system.is required due to the reactor decay he'at, it shall remain in operation throughout the test, i
This will help prevent transients in reactor water level.
NOTE When using shutdowr. cooling with the reactor recirculation pumps not running either the recircula-tion or B) pump suction valve (MO-202-4A or discharge valves (MG-202-5A or B and MO-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.
l' 14.
The Integrated Primary Containment Leak Rate Test will con-sist of five phases.
Each phase will have a definite starting and ending point and is so defined because of the different types of setivities that will occur in each.
a.
The preparation phase (phase 1).
b.
The pressurization and stabilization phase (phase 2).
c.
The measured leakage rate at 48 psig phase (phase 3).
d.
The induced leakage phase at 48 psig (phase 4).
e.
The d pressurization phase (phase 5).
NOTE The signed and dated events log started by the responsible 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-AppgOVED s
arate section titled "Special Changes".
M 22'83 6 of 77 D. O. 9 o
e DTS 1600-7 Revision 6 15.
Any change to instrumentation sensor placement or computer
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program must be reviewed at the same level as a temporary procedure change. Deletion of an result of failed instrumentation)y data points (f.e. as a s
must also be reviewed at this level.
1 F.
PROCEDURE 1.
Test Preparation (Phase 1).
a.
Prior to sealing the drywell and pressure suppressien chamber for pressurization, the pre-test portion of the following checklists must be completed:
CHECXLIST DEPARTMENT VERIFIED 1.
Maintenance 2.
Operations 3.
Instrument Mechanics 4.
Technical Staff Pretest preparation complete.
2.
Pressurization and Stabilization (Phase 2).
4 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)
Perform the vacuum breaker test per DTS 1600-16.
(2).After compfetion 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 l
A0-2(3)-1601-61 & 62.
l (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 l
leakage.
Special attention should be paid to the drywell t
to torus vacuum breaker position' indications, electrical penetrations, and small penetrations which cannot be local leak rate tested.
i APPROVED 7 of 77 ME 22 '83 D.O.c 9
t s
DTS 1600-7 Revision 6 c.
If sources of leakage are fcund 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.
1 NOTE The results of the local leak rate test or the estimated leakage rate from all repaired leaks must be added to the results of Type A test at 48 psig leak rate calcu-lation to determine a leakage rate at the beginning of the test.
If this resultant leak rate is above La, a Reportable Occurrence must be initiated.
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 tenperature changes is less than 0.5'F/ hour / hour averaged cver the last two (2) hours.
APPROVED
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' 19R 22 '83 8 of 77 D.O.S. R.
r 0
DTS 1600-7 Revision 6 NCTE i
A continuous monitoring of the con-tainment penetratior.s should be maintained during the pressuriza-tion phase.
If any leaks are found, an estimate of the leakage rate must be made before any repairs, are attempted.
Containment stabilization complete.,
h.
Perfonr. local leak rate test, at 48 psig, on personnel interlock docr 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 requires 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 bour 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.
Method A (12. hours minimum Phase 3 duration) t a.
Check 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 half hour:
(1) Time and date.
(2) Ambient temperature, pressure and relative humidity of the reactor building.
(Data sheets 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.
(Datasheet1).
...L APPROVED 9 of 77 l
D. O. S. R.
l
r.
DTS 1600-7 Revision 6 (6) Reactor water temperature (Data sheet 2).
(7)
Reactor water level.
(Datasheet2).
(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 tiu aid of a computer, the following infomation at least once,every half hour.
(1) Average temperr.ture by volume ('F).
(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 ).
g l
(8) Calculated leak rate (L ) and 95% confidence Ifmits.
t
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d.
Record the information in F.3.c. (Data sheet # 2 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 43 psig.
De,ta 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 l
1eakage data. The upper confidence limit of the calculated leak rate is then computed.
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.
l 1
APPROVED l
MAR 22 '83 10 of 77 D. O. S. R.
a DTS 1600-7 Revision 6 i,
i.
The measured leak rate phase can be tenninated 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
.t (3) The last camputed upper 95% confidence limit of the calculated leak rate based or Total Time calculations shall be less than 0.75 La.
Verified (4) The mean of the measured leak rates based en 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
- A Verified i
(5) At least twenty (20) data points snall be provided for s-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 leak 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 22 M D.O.S.R.
1
.*0, DTS 1600-7 Revision 6 D.
Record the following data at least once every hour:
(1) Time and date.
(2) Ambient temperature, pressure and relative humidity of the reactor building.
(Data sheets 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 camputer, the following information at least once every hour.
~
(1) Average temperature by volume ('F).
(2) Average vapor pressure by volume (psi).
(3) Average containment volume weighted teaperature
(*F).
l (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 the information in F.3.c. (Data sheet 4).
e.
Plot the infomation in F.3.c.(5) thru (8) as a function of time.
APPROVED ME 22 '83 12 of 77 D. O. S. R.
DTS 1600-7 Revision 5 f.
Leakage rate me surements will be made at an average containment F. essure (over the time period of the test) of at least 48 psig. Data taking will continue for at least 24 consecutive hours.
g.
Campare 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 (1.25 per day) and La (1.6% per day).
If the leakage rate approaches 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 below Lt, at 48 psig, phase 4 can begin immediately.
If not, thc 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)
As Found Local Leak Rate (wt%/ Day)
As Lef t Local Leak Rate (wt%/ Day)
Total Leakage Rate As Found/As Left
/
(wt %/ Day)
Verified 4.
48 psig Induced Leak Rate Phase (Phase 4).
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 phat.e 3 calculated leak rate. The new leakage rate is then calculated oy the same mathod which was used during phase 3 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.
If Method A was used fc,' phase 3 calcu-lations, phase 4 must be conducted for a lengtr of time equal to at least one-half that of phase 3.
The suction to the flowmeter for the induced leakage a.
should be taken from the suction line to the CAM mon-itor. The moisture separator can be installed if desir-able. The flowmeter discharge shall be vented to the reactor building.
The induced leakage as measured on the flowmeter must be between 10.27 and 17.12 SCFM.
i b.
Request the Radiation Protection Department to obtain a i
drywell air saniple. This can be obtained from the dis-charge of the ILRT flowmeter.
(See Checklist #, attached).
APPROVED 13 of 77
)W 22 'E hnon
DTS 1600-7 Revision 6 In conjunction with the sir sampling, begin recording data c.
(
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 onca every hour until sufficient data is obtained to adequately fulfill the requirements.
e.
If the ind::::ed leakage cannot be accurately detected, an investigation of the cause should be made, corrective actions taken, and the induced leakage phase restarted followin: repressurization to 48 psig. An evaluation and the corrective acticas should be included in the report to the NRC.
Superimposed Leak Rate:
SCFM 1440 MIN T+459.69*R 14.696 PSIA 100% =
Day 519.69*R p
V0L WT%/ DAY WHERE, T = Induced phase average containment temperature,
'F.
P = Induced phase average containment t
- pressure, PSIA.
VOL = Free volume of the containment.
~
fts Induced phase calculated leak rate:
WT;/ Day L
Induced Phase L / Measured Phase
)
+L Superimposed 10.25(1.t Calculated Leak Rate l Calculated Leak Rate?
Leak 9 ate J
_(
/
+
1 0.4 Wf%/ 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 i
F.4.b. are below the allowable activity limits.
APPROVED 14 of 77 2 '83 D. O. S. R.
DTS 1600-7 Revision 6 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 butiding vent.
After depressurization is complete, nomal station dry-e.
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 Departnent, 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 remove all test equipment 'from the primary containment.
h.
The responsible Tech Staff Engineer should notify the Shift Engineer of satisfactory completion of the test so that all valves with altered position status can be returned to nomal.
i.
CLOSE the torus access hatch after the removal of all instrumentation. Tech Staff shall perfom a final local v
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.
l 3.
DTS 1600-7, Operating Department, Checklist 3, attached.
4.
DTS 1600-7, Instrument Maintenance Department, Checklist 4, attached.
S.
DTS 1600-7, Technical Staff, Checklist 5, attached.
6.
DTS 1600-7, Radiation Protection, Checklist 6, attached.
H.
TECHNICAL SPECIFICATIONS REFERENCES 1.
Section 4.7.A.2.
APPRoygg 2.
Section 3.6.B.2.
15 of 77 D.O. S.g
OTS 1600-7 Revision 6 MECHAN' CAL MAINTENANCE DEPARTMENT CHECKLIST 1
(
A.
Pretest Requirements.
1.
CLOSE equipment hatch and notify the Tech Staff to perfom a local leak rate test.
Verified 2.
CLO3E both torus. access hatches after verifying that the Instrument Mechanics have installed all the required in-strumentation. Notify Tech Staff to perfom 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, afterfilters 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)-
2001-1 A and 2(3)-2001-101 A.
Infom the Shift Engineer upon k
canpletion.
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, 1
APPROVED MAR 22 *83 16 of 77 D. O. S. R.
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DTS 1600-7 Revision 6 2.
Disassemble all the air compressor manifold piping.
J.
Verified 3.
Upon the removal of all test instrumentation, CLOSE the open torus access hatch and request Tech Staff to perfonn a local leak rate test.
Verified 4.
Replace 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 Shift Engineer.
Verified e.
e 4
e APPROVED W22%
17 of 77 D.O.S.R.
~
DTS 1600-7 Revision 6 ELECTRICAL MAINTENANCE DEPARTMENT
(
CHECKLIST 2 A.
Pretest Requirements 1.
If fans are required in the torus and/or drywell, install them at the locations determined by the Tech Staff Engineer.
Verified:
instalisd not required 2.
Vent each indexer housing to the drywell.
Verified 3.
In order te prevent ECCS initistion fc11owing 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 9023)-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
-32 Lift Coil Wire 13 12E2461 12E3461 287-1018 902
-33 Lift Coil Wire 13 12E2462 12E3462 287-102B 902
-33 Lift Coil Wire 13 12E2462 12E3462 1530-108 902(3 -32 Lift Coil Wire 13 12E2437 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 9023)-32 Lift Coil liire 13 12E2437 12E3437 1530-234 902 3)-33 Lift Coil Wire 13 12E2438 12E3438 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 12E2/38(12E3438)
B.
Post Test Requirements.
1.
Remove the fans (if installed) from the torus /or drywell after completion of the test.
Verified APPROVED M 22 *83 18 of 77 D. O. S. R.
DTS 1600-7 Revision 6
{
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 E90-1030 902(3 -17 Block in 12E2464 12E3464 287-101A 902
-32 Lift Coil Wire 13 12E2461 12E3461 287-102A 902
-32 Lift Coil Wire 13 12E2461 12E3461 287-1018 902
-33 Lift Coil Wire 13 12E2462 12E3462) 237-1023 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) 12E2437 ((12E3437) 1530-134 902 3 -32 Lift Coil Wire 13 1530-234 902 3)-33 Lift Coil Win 13 12E2438(12E3438) 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 ho'using.
Verified
.a l
l APPROVED 19 of 77
$ 22 '83 D.O.S.R
DTS 1600-7 Revision 6 OPERATING DEPARTMENT f.
CHECKLIST 3 A.
Protest Requirements 1.
The following 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 then as indicated on the attached list and hanging caution ca rds.
NOTE
~
Closure of the containment isola-tion valves will be done by the nonnal 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-OF-SERVICE.
b.
Close the sump pump discharge maintenance valves 2(3)-
2001-2A or 2B 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 CHECXLIST 1, Step A.4).
d.
Clear the outage on the sump pumo and verify manual discharge valves 2(3)-2001-2A and 2B are OPEN.
Verified APPROVED 20 of 77 N 22 '83 D. O. S. R.
0-,4--,
,---4
,--r
-e
,.- +,
DTS 1600-7 Revision 6 4.
Prepare the drywell floor drain sump as follows:
a.
Pump down the drywell floor drain sump &S 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 1028 and then tue 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.4).
d.
Clear the outage on the sump pump and verify manual discharge valves 2(3)-2001-102A and 102S 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.
Verifted 6.
Isolate the jockey pump from the appropriate LPCI loop by CLOSING the following valves:
s fi0-2(3)-1501-32A 2.(3)-1501-66A Notify the maintenance department in order that the contain-ment spray header flange cari 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 APPRovgn 21 of 77 22 '83 D. O. S. R.
ey v
e.
y my..--,,.
,-wr-.
c-
-.7.
-y,,,,,y
,-rw, r-,7
,,-y,-,,,--yy
,y,-
g w.p-sy, w--.,,
-,y--
a DTS 1600-7 Revision 5 10.
If the reactor vessel water temperature can remain at approx-i.mately 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.
Immediately 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 Perfomance of this checklist will put the systets affecting primary containment in the following configuration:
SYSTEM CONDITION s
Main Steam Isolated, Drained,' Vented Reactor Feedwater Isolated (Water filled, ready l
for operation)
Reactor Building Closed Cooling Supply closed, Return Open i
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 a
water temperature.
Clean Demin to Drywell Isolated 1
Drywell Floor & Equipment Drains Isolated Vented l
Service Air to Drywell Isolated i
Drywell Pneumatic Isolated, Vented Isolation Condenser Isolated, Vented i Reactor Recirculation Filled, Pumps Off Head Cooling Isolated, Vented CRD Return Isolated 5
' APPROVED 22 of 77 l
D.O. S. R.
o DTS 1600-7 Revision 6 B.
Post Pressurization Requirements 1.
CLOSE VALVE 2-1501-28A(3-1501-288) upon notification from the Tech Staff.
Verified 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 4
shutdown cooling heat exchanger inlet valve.
Verified 3.
After the Maintenance Department removes the. temporary flinge from the containment spray line, OPEN the following valves:
MO-2(3)-1501-32A 2(3)-1501-66A Verified C.
Post Test Requirements 1.
Return all previously altered equipment back to its nomal state.
Verified l
t l
1 l
eb 23 of 77 D.O.S.R.
~
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP PCNT LOCATION LINE DESIRED NORMAL P&XD NO.
ELEY. AZI.
SIZE 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-EA C
(Gland Seal Leak-Off) 2-220-9A C
(Viv Body Drain) 2-220-10A C
(Viv Body Drain)
C (MSL Test Conn - 2 Va h s) 12 105B 517-6 10 20 A0-2-203-1B C
Primary Steam A0-2-203-2B C
Primary Steam 3/4 2-220-7B C
Gland Seal Leak-Off) 2-220-88 C
Gland Seal Leak-Off) 2-220-9B 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 Drain) 2-220-10C C
(Viv Body Drain)
C (MSL Test Conn - 2 Valves) 12 105D 517-6 355 20 A0-2-201-ID.
C Primary Steam A0-2-203-2D C
Primary Steam 3/4 2-220-7D C
Gland Seal Leak-Off) 2-220-80 C
Glanc Seal Led-Off) 2-220-9D C
Viv Body Drain) 2-220-100 C
Viv Body Drain)
C MSL Test Conn - 2 Valves) 12 106 515-0 2
MO-2-220 4 C
MSL Drain MO-2-220.!
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
MSLVentPath)
MO-2-220-908 0
MSL Vent Path)
MO-2-220-90C 0
MSL Vent Path)
MO-2-220-90D 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 Flow Instr.
2-220-12A 0
APPROVED 24 of 77 22 T3 D. O. e. g,
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&tD NO.
ELEV. AZI.
SI?E VALVE NUMBER VALVE POSITION DESCRIPTION 12 115B 513-9 275 3/4' 2-220-11B 0
MSL F1ow Instr 2-220-123 0
2-220-11C 0
2-220-12C 0
2-220-11D 0
2-220-120 0
20 123 513-9 45 6
M0-2-3702 C
R8CCW 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 2-1601-4D 0
25 125 513-0 332 18 A0-2-1601-21 C
N Purge & Vent g
A0-2-1601-22 C
A0-2-1601-55 C
A0-2-1601-56 C
3/4 2-1699-72 C
(Test Connection) 4 2-8599-544 0
(Pumpback Syst) 2-8599-545 0
1 MO-2-1601-57 C
N Make-Up 2
A0-2-1601-58 C
A0-2-1601-59 C
1/4 2-8599-526 C
(Test Connection) 1 2-8599-558 0
(Purpback Syst) 2-8599-552 0
25 304 509-0 270 18 A0-2-1601-20A C
Torus Vacuum Relief A0-2-1601-208 C
NOTE: FAIL OPEN) 3/4 2-1599-50 C
TestConn-2 Valves) 2-1699-51 C
Test Conn - 2 Valves)
D/W Cooler Damper Control N, Supply C
25 125 572-0 145 18 A0-2-1601-23 C
Drywell Vent A0-2-1601-24 C
i 2
A0-2-1601-62 C
6 AG-2-1601-63 C
3/4 C
(Test Connection @
EL 570-0 near 1601-23 viv.:
318 509-0 95 18 A0-2-1601-6 hPPROVM5V'"*
~
25 of 77 MAR 22 '83 D. O. S. R.
DTS 1600-7 Revision 6 UNIT 2VALVELINEUP(Cont'd.)
PENT LOCATION LINE DESIRED NCRMAL P&ID NO.
ELEV. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 25 318 509-0 95 2
A0-2-1601-61 C
Torus Vent 3/4 2-1699-002A C
Test Connect 2-1699-0028 9 EL 509-0 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 FCV-2-8501-38 C
25 143 547-6 120 1/2 FCV-2-8501-5A C
Drywell Air Sample FCV-2-8501-5B C
FCV-2-9205A C
FCV-2-9205B C
FCV-2-9206A C
FCV-2-9026B C
2-2252/47/1 C
2 Valves) 2-2252/47/2 C
2 Valves) i 2-2252/47/3 C
2 Valves) 2-2252/47/4 C
2 Valves) 2-2252/47/5 C
(2 Valves) 2-2252/47/6 C
2 Valves) 2-2252/47/7 C
2 Valves) 2-2252/47/8 C
2 Valves) l 2-2252/47/9 C
2 Valves) 2-2252/47/10 C
2 Valves t
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 ValvesJ 2-2252/47/18 C
2 Valvesl 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) 2-2252/47/24 C
1 Valve) 26 147 564-0 295 2h FCV-2-205-2-3 0
Rx Head Cooling MO-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) l 2-205-2-6 C
(Test Connection)
~
APPROVED 26 of 77 ER 22 '83 l
D. 0. s. R.
DTS 1600-7 Revision 6 UNIT 2 YALVE' LINEUP (Cont'd.)
PENT L0r.ATION LINE DESIRED NORMAL P&ID NO.
ELEV. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 2-2099-323 C
Drain 2-2099-324 C
Drain 2-2099-325 C
Drain) 2-2099-326 C
Crain) 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
128A 565-0 210 1
2-263-2-128 0
1288 565-0 210 1
2-263-2-14B 0
129A 564-0 70 1
2-263-2-12A 0
1298 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 566 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
i l
k'.
2-263-2-300 0
2-263-2-30E O
2-263-2-306 0
2-263-2-30H 0
2-263-2-30J 0
2-263-2-30K 0
2-263-2-21A 0
2-263-2-218 0
2-263-2-22A 0
2-263-2-228 0
37 136A-E 517-6 270 3/8 Tip Ball Valves (5)
C Tip Drive Power Breakers (2)
Racked Out Drycal1 0, Anal.
Cab Bkrs il Racked Out
- 2 Racked Out
- 3 Racked Out
- 4 Racked Out 1428 540-0 245 1
i-
' 263-2-30M 0
2-263-2-30N O
2-263-2-30P 0
2-263-2-30R 0
2-263-2-30T 0
2-263-2-30U 0
2-263-2-30V 0
APPROVED 27 of 77 2D 1
D. O. e. g,
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&ID NO.
ELEY. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 1428 540-0 245 1
2-263-2-30W 0
2-263-2-21C 0
2-263-2-21D 0
2-263-2-22C 0
2-263-2-22D 0
131A 528-0 110 1
2-263-2-24 0
131B 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
2-220-66F 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
2-220-16B 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
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
134D 510-0 270 1
2-220-14B 0
26 122 548-8 265 3/4 A0-2-220-44 C
Rx Water Sample A0-2-220-45 C
l 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) l 2-1402-32A C
(TestConnection) 2-1402-33A C
10 MO-2-1402-25A C
2/4 2-1402-5A C
(Drain /TestConnection) 2-1402-52A C
(Drain / Test Connecticn)
APPROVED 2-1402-7A C
(Drain) teR221G 28 # 77 D.O.S.R.
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Ccit'd.)
C PENT LOCATION LINE DESIRED NORMAL P&XD NO.
ELEY. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 27 149A 564-9 20 3/4 2-1402-14A C
(Drain)'
2-1402-15A C
(Pump Drain) 16 MO-2-1402-3A 0
2-1402-29A 0
Manual Isol.
12 2-1402-2A C
2-1402-29B 0
Manual Isal.
2-1402-10A C
2-1402-10B C
27 149A 564-9 155 10 2-1402-6B 0
Core Spray 3/4 2-1402-35B C
(Drain) 2-1402-46B C
(Gland Seal Leak-Off) 2-1402-32B C
(TestConnection) 2-1402-33B C
10 MO-2-1402-25B C
3/4 2-1402-5B C
(Drain /TestConnection) 2-1402-E2B C
(Drain / Test Connection) 2-1402-78 C
Drain) 2-1402-14B C
Drain) 2-1402-158 C
Pump Drain) 16 MO-2-1402-38 0
(-
12 2-1402-2B C
b7 310A 509-0 118 8
MO-2-1402-4A C
Core Spray Test Line 3108 509-0 238 8
MO-2-1402-48 C
28 141A 542-6 160 14 HC-2-1301-1 0
Isolation Condenser MO-2-1301-2 0
3/4 2-1301-34 C
(TestConnection) 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
(Instrumentation) 2-1301-22 0
(Instrumentation) 2-1301-27 0
(Instrumentation) 2-1301-28 0
(Instrumentation) 3/4 A0-2-1301-17 C
(Vent) 2-1301-606 C
(Drain) 2-1301-607 C
(Drain)
A9-2-1301-20 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) l 2-1301-601 C
M 1301-4 C
(Drain)
APPROVED 3/4 2-1301-18 C
(Dr in) 2-1301-19 C
(Drain) l WR 22 '83 2-1301-32 C
(TestConnection) 2-1301-33 C
(Test Connection) l D.O.S n.
- ' ' 77
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
I PENT LOCATION LINE DESIRED NORMAL P&tD 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) 3/4 2-1501-23A C
Test Connection) 2-1501-79A C
Vent) 2-1599-15A C
Drain) 29 1168 513-9 263 16 M0-2-1501-22B C
LPCI' Injection 2-1501-26B 0
1/2 2-1501-91B C
(Drain) 3/4 2-1501-238 C
(TestConnection) 2-1501-798 C
(Vent) 2-1599-15B C
(Crain) 29 310A 509-0 118 14 MO-2-1501-20A C
LPCI Test MO-2-1501-38A C
3/4 2-1501-87A C
(TestConnection) 29 310B 509-0 238 14 MO-2-1501-20B C
LPCI Test l
M0-2-1501-388 C
3/4 2-1501-87B C
(TestConnection) 1
.~
c.
145 547-6 210 10 MO-2-1501-278 C
2-1501-298 C
3/4 2-1501-30B C
(TestConnection) 2-1501-45B C
(Vent) 29
, 150A 527-1 160 10 MO-2-1501-27A C
3/4 2-1501-45A C
(Vent)
MO-2-1501-328 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
i 3/4 2-1501-40A C
(Drain /TestConnection) 29 311B 509-0 240 6
MO-2-1501-188 C
MO-2-1501-198 C
3/4 2-1501-408 C
(Drain / Test Connection) 29 14 MO-2-1501-5A 0
LPCI Suction MO-2-1501-5B 0
MO-2-1501-5C 0
MC'2-1501-50 0
APPROVED 2-1501-6D C
2-1501-6A C
30 of 77 2 2 '83 l
D. O. S. R.
APPROVED DTS 1600-7 H& 22 '83 Revision 6 D. O. S. R.
UNIT 2 YALVE LINEUP (Cont'd.)
{
PENT LOCATION LINE DESIRED NORMAL P6ID NO.
ELEV. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 29 14 2-1501-73A C
i 2-1501-73B C
2-1501-70B C
2-1501-70A C
2-1599-27A C
2-1599-278 C
2-1501-31A C
2-1501-310 C
2-1501-31C C
2-1501-31D C
2-1501-66A C
ECCS Fill 2-1501-668.
C 30 113 547-10 300 10 MO-2-1201-1 C
Rx Cleanup MO-2-1201-2 C
MO-2-1201-3 C
1/2 2-1299-4 C
(Drain / Test, Connection) 2-1299-5 C
2-1299-6 C
2-1201-31 C-(Vent on Clean-Up Aux Puap 2-1201-32 C
2-1299-11 C
CU Ndr Test Tap 111A 530-8 25 16 MO-2-1001-1A C
Shutdcwn 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
(Pump Suction) l MO-2-1001-2B C
(Pump Suction) 3/4 2-1001-92A C
Drain / Gland Seal) i 2-1001-928 C
Drain / Gland Seal) t 2-1001-93A C
Drain) 2-1001-938 C
(Drain) 2-1001-47A C
(Vent) 2-1001-48A C
(Vent) 2-1001-206A C
Manual Bypass Around 2A Va' 2-1001-2068 C
Manual Bypass Around 2B Va' 32 1118 530-8 70 16 MO-2-1001-1B C
Shutdown Cooling 3/4 2-1001-888 C
(Gland Seal Leak-Off) 2-1001-46B C
(Drain) 2-1001-45B.
C (Drain) 14 MO-2-1001-2C C
(Pump Suction) 3/4 2-1001-92C C
(Drain /GlandSeal) 2-1001-93C C
(Drain) 2-1001-478 C
(Vent) 2-1001-488 C
(Vent) 2-1001-200 C
2-1001-206C C
Manual Bypass Around 2C Va' l
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 0
SDC to HRSS 32 116B 513-9 263 14 MO-2-1001-5B C
Shutdown Cooling 31 of 77
075 1600-7 Revision 6
~
UNIT 2 YALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&ID NO.
EL2V. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 32 1168 513-9 263 3/4 2-1001-148 C
(Gland Seal Leak-Off) 2-1001-10B C
2-1001-288 C
(Drain) 33 130 581-0 340 1-1/2 2-1101-1 0
SBLC 1/2 2-1199-104 C
(Drain) 2-1199-105 C
2-1199-103 C
(Test Connection) 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 2-301-500 C
CRD (Return Test Conn) 2-301-501 C
35 119 527-6 275 3
2-4327-500 C
Clean Demin Water 37 112A 547-5 8
1/4 C
Drywell Cooler Damper.
Control (11 Valves)
C (5 Valves) 6 1/4 C
(25 Valves) 1128 547-5 21 1/4 37 121 527-6 283 1
2-1601-48 0
DW Pneumatic A0-2-4722 C
C (Test Connection by 4722) 1/4 2-4741-20C 0
(TestVent) 37 1390 537-6 280 1
A0-2-4720 C
DW Pneumatic A0-2-4721 C
C (Test Connection between 1/4 4720 and 4721) 2-4771-500 0
Test Vent) 2-4771-501 0
Test Vent) 38 120 527-6 280 3
2-4630-500 C
Service Air 3
2-4609-501 C
0 (Hose Conn Col H-42) 510-0 480-0 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) l 3
A0-2-2001-3 0
117 512-3 185 3
A0-2-2001-105 C
DW Floor Drain l
APPROVED l
32 of 77 NAR 22 '83 D. O. S. R.
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRE 6 NORMAL P&ID NO.
ELEY. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRI
'M 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
MO-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
S0-2-2301-29 C
S0-2-2301-30 C
2-2301-43 C
Test between 10-2301-29 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
317A 509-10 190 3/4 2-2301-41A C
HPCI Cond Return s,.
3/4 2-2301-42A C
(Test Conn) 51 312 497-0 200 3/4 2-2301-41B C
HPCI Drain Pot Drain 3/4 2-2301-42B C
(Test Conn) 2 2-2301-33 0
2-2301-47 0
1 50-2-2301-32 C
51 310A 509-0 118 4
MG-2-2301-14 C
HPCI Min Flow BKR for 2301-14 Racked Open 51 16 MO-2-2301-35 C
HPCI Suction MD-2-2301-36 C
s MO-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"
A0-2-2599-28 C
ACAD Sh 1 of 2 3/4" 2-2599-11B' C
ACAD 3/4" 2-2599-12B C
ACAD APPROVED 204B 532 195' 1"
2-2599-25B 0
ACAD M 22 '83 33 of 77 D. O. S. R.
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&IO NO.
ELEV. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 707 316B Torus 305 1"
A0-2-2599-3B C
ACAD Sh 1 3/4" 2-2599-14B C
ACAD of 2 3/4" 2-2599-138 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 0
ACAD AIR PRESSURE ACAD AIR COMPRESSOR OFF DRAIN
~
s 125 572 145" 1"
A0-2-2599-4A C
FCV-2-2599-5A C
i A0-2-2599-48 C
FCV-2-2599-5B C
3/4" 2-2599-15A C
l 2-2599-16A C
1 l
2-2599-158 C
l l
2-2599-16B C
707 202Y 534 165" 1/2" S0-2-2499-2A C
CAM Sh 2 of 2 1/2" S0-2-2499-1A C
CAM 1/2" 2-2499-7A C
CAM APPROVED Q.-
l NAR 22 '83 34 of 77 D. O. S. R.
DTS 1600-7 Revision 6 UNIT 2 VALVE LINEUP (Cont'd.)
t PENT LOCATION LINE DESIRED NORMAL P&ID NO.
ELEY. 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" S0-2-2499-29 C
CAM 1/2" S0-2-2499-1B C
CAM 1/2" 2-2499-7B C
CAM 1/2" 2-2499-88 C
CAM 316B Torus 305*
1/2" S0-2-2499-4B C
. CAM 1/2" S0-2-2499-38 C
CAM 1/2" 2-2499-10B C
CAM 1/2" 2-2499-98 C
CAM l
APPROVED MAR 22 '83 l
35 of 77 D.O.S. R.
DTS 1600-7 Revision 6 UNIT 3 VALVE LINEUP PENT LOCATION LINE DESIRED NORMAL P&ID NO.
ELEV. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 356 X-115A 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 295 3-1601-4D 0
353 X-123 513-9 45 6
MO-3-3702 C
RBCCW INLET 353 X-124 513-9 48 6
M0-3-3703 0
RSCCW OUTLET MO-3-3706 0
360 X-116A 513-9 83 16 MO-3-1501-22A C
LPCI INJECTION X-1168 263 MO-3-1501-22B C
3/4 3-1599-2A C
DRAIN 3-1599-ZB 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 MO-3-1501-208 C
l MO-3-1501-388 C
MO-3-1501-87B C
TEST CONN 1
X-311A 509-0 120 6
MO-3-1501-18A C
LPCI TORUS SPRAY MO-3-1501-19A C
X-311B 240 MO-3-1501-188 C
MO-3-1501-198 C
360 X-150A 547-6 210 10 MO-3-1501-27B C
3-1501-308 C
3-1501-298 C
X-145 MO-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-3-1501-5C 0
MO-3-1501-5D 0
14 3-1501-31A C
14 3-1501-31B C
14" 3-1501-31C C
3-1501-31D C
345 X-105A 517-6 5
20" A0-3-203-1A C
PRIMARY STEAM A0-3-203-2A C
l APPROVED 36 of 77 N4R 22 eg I
D. O..e
DTS 1600-7 Revision 6 UNIT 3 VALVE LINEUP (Cont'd.)
/*
PENT LOCATION LINE DESIRED NORMAL P&fD NO.
ELEV. 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 D/W Cooler Damper Control N2 Supply C
Inst. Air Supp1v C
Air Supply at iio?
C Air Supply Drain C
l 345 X-1058 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-OFF 3-220-8B C
GLAND SEAL LEAK-OFF 3-220-98 C
YLV BODY LRAIN i
3-220-10B C
i C
2 MSL TEST CONN l
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
VLV BODY DRAIN) 3-220-10C C
VLV BODY DRAIN)
C 2 MSL TEST CONN) 345 X-105D G17-6 355 20" A0-3-203-1D C
PRIMARY STEAM A0-3-203-2D C
3/4" 3-220-70 C
GLAND SEAL LEAK-OFF 3-220-80 C
GLAND SEAL LEAK-OFF 3-220-90 C
VLY BODY DRAIN 3-220-100 C
C (2 MSL TEST CONN) 345 X-106 515-0 0
2" MO-3-220-1 C
MSL DRAIN MO-3-220-2 C
MO-3-220-3 0
MO-3-220-4 C
3/4" 3-220-5 C
(TEST CONN) 3-220-6 C
2" MO-3-220-90A 0
MO-3-220-908 0
MO-3-220-90C 0
MO-3-220-900 0
APPROVED.
37 of 77 MAR 22 '83 D.O.Sg
DTS 1600-7 Rsvision 6 UNIT 3 YALVE LINEUP (Cent'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 HOSE CONN) 3-3025-501 0
345 X-135B 513-9 275 3/4" 3-220-11A 0
MSL FLOW INSTR 4
X-135C 3-220-12A 0
X-135E 3-220-118 0
X-135F 3-220-12B 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 PURGE LINE 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
l 3"
3-8502-500 C
BYPASS VLV 1h" MO-3-1601-57 C
N, MAKE UP A0-3-1601-58 C
N'z MAKE UP A0-3-1601-59 C
3-1601-500A C
TEST CONN. BY 20A m,
356 X-304 509-0 270 18" A0-3-1601-20A C
TORUS VACUUM RELIEF A0-3-1601-20B C
(NOTE:
FAIL OPEN) 3-1601-5008 C
(TEST CONN. 10) 356 X-125 572-0 145 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 l
and 53 C
1601-60 and 61 3-1601-527 C
TEST CONN NEAR N MAKE UP l
356 X-309A 498-7 155 1/2" FCV-3-8501-1A C
TORUS SAMPLE FCV-3-8501-1B~
C C
356
'X-204 532-6 190 1
FCV-3-8501-3A C
SAMPLE RETURN FCV-3-8501-3B C
C APPROVED l
s 38 of 77 l
D. O. C..
-3 mr-"'"r+vv - WP
+tm'+9
*'s2=~,,ew
- -~
p-w-----8
- w-w--N ee---m-umi e--+=vre---ww
-w-----**
="
w-
DTS 1600-7 Revision 6 UNIT 3 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&ID NO.
ELEY. 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-3-92068 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
3-8507-505 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
l 3-8507-517 C
l 3-8507-518 C
3-8507-519 C
3-8507-520 C
3-8507-521 C
l 3-8507-522 C
l 3-8507-523 C
357 X-136A-E 517-6 90 3/8" A Tip Ball Viv C
8 Tip Ball Viv C
C Tip Ball Viv C
D Tip Ball Viv C
E Tip Ball Viv C
Tip Power Skr #1 Racked Open Tip Power Bkr #2 Racked Open l
357 X-147 564-0 295 2"
3-205-2-3 0
Rx HEAD COOLING I
MO-3-205-2-4 C
3/4" 3-205-2-1 0
DRAIN l
3-20E-2-2 0
DRAIN 3-205-2-5 C
TEST CONN.
3-220-48 0
Rx HEAD VENT 3-220-49 0
X-133A 563-0 70 1"
3-220-53 Rx VESSEL INSTR A PRovgo 39 of 77 6.o s.a.
DTS 1600-7 Revision 6 UNIT 3 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P1ID NO.
ELEY. 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=263-2-125 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"
3-263-2-1dA 0
3-263-41A 0
X-134E 1"
3-263-2-16B 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 0 263-2-303 0
3-263-2-30C 0
3-263-2-300 0
3-263-2-30E 0
3-263-2-30G 0
3-265-2-30H 0
~
3-263-2-30J 0
3-263-2-30K 0
s.
X-142S 245 1"
3-263-2-21C 0
3-263-2-210 0
3-263-2-22C 0
3-263-2-220 0
3-263-2-30M 0
3-263-2-30N O
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 15 3-220-66A 0
D/W 0, Anal Cab BRKS #1 RACKED OPEN
- 2 RACKED OPEN
- 3 RACKED OPEN
- 4 RACKED OPEN 3-220-66B 0
3-220-66C 0
0 D
X-151 530-0 205 1"
,s 15t22113 4
' 77 D.O.S.R.
DTS 1600-7 o
Revision 6 UNIT 3 VALVE LINEUP (Cont'd.)
(*
PENT LOCATION LINE DESIRED NORMAL P&fD NO.
ELEY. AZI 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"
3-220-16A 0
X-131B 270 1"
3-220-15B 0
X-131C 1"
3-220-16B 0
3-252-2-4A 0
X-130A 1"
3-262-2-3A 0
X-131A l'
3-262-2-3B 0
X-130E 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
3-253-2-26 0
3-263-2-32 0
X-131E 1"
3-220-138 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
e 3-220-42 C
TEST CONNECTION 3-220-43 C
358
'X-149A 564-9 20 10" 3-1402-6A 0
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-149B 564-9 155 10" 3-1402-6B 0
CORE SPRAY MO-3-1402-25B C
3/4" 3-1402-32B C
TEST CONN 3-1402-33B C
16 MO-3-1402-3B 0
3-1402-28 C
358 X-310A 509-0 118 8"
MO-3-1402-4A C
CORE SPRAY TEST LINE X-3108 238 8"
MO-3-1402-48 C
~
3-1402-468 C
3-1402-35B C.
359 X-108A 14" h0-3-1301-1 0
APppoya-MO-3-1301-2 0
~
e I
u 3/4" 3-1301-34 C
(TEST CONN) 5 22'83 D. O.S.g
DTS 1600-7 Revision 5 UNIT 3 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&XD NO.
ELEV. AZI SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 359 X-108A 3/4" 3-1301-35 C
(TEST CONN)
C 2 VLYS GLAND SEAL LEAK-OFF 1"
3-1301-21 0
3-1301-22 0
X-132D 3-1301-27 O
X-132A 3-1301-28 0
X-108A 3/4" A0-3-1301-17 C
A0-3-1301-20 C
3-1301-602 C
TEST CCNN 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" M0-3-1301-3 C
ISOLATION COND MO-3-1301-4 C
3/4" 3-1301-32 C
(TEST CONN) 3-1301-33 C
3-1301-18 C
(DRAIN) 3-1301-19 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
SHUTDOWN 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
MO-3-1001-28 C
3/4" 3-1001-92A C
(BRAIN) 3-1001-928 C
DRAIN 3-1001-88A C
GLAND SEAL LEAK-OFF 363 X-1118 530-7 70 16" MO-3-1001-1B C
SHUTDOWN COOLING 3/4" 3-1001-45B C
DRAIN APPROVED 42 of 77 MAR 22 '83 D. O. S. R.
DTS 1600-7 Revision 6 l,
UNIT 3 VALVE LINEUP (Cont'd.)
PENT LOCATION LINE DESIRED NORMAL P&ID NO.
ELEY. AZI.
SIZE VALVE NUMBER VALVE POSITION DESCRIPTION 363 X-1118 530-7 70 3/4" 3-1001-46B C
DRAIN 3-1001-47B C
3-1001-488 C
14" MO-3-1001-2C C
3/4" 3-1001-92C C
DRAIN 3-1001-88B C
GLAND SEAL LEAK-OFF 363 X-116A 513-9 83 14" MO-3-1001-5A C
SHUTDOWN COOLING 3/4" 3-1001-10A C
GLAND SEAL LEAK-OFF 3-1001-14A C
l 3-1001-28A C
3-1001-29A C
363 X-116B 513-9 263 14" MO-3-1001-5B C
SHUTDOWN COOLING 3/4" 3-1001-10B C
GLAND SEAL LEAK-OFF 3-1001-14B C
3-1001-288 C
l 3-1001-298 C
364 X-138 581-0 340 1"
3-1101-1 0
SBLC 3/4" 3-1199-005 C
2 Vivs VENT:
IN DW
-006 C
TEST CONN 3-1199-9 C
2 Vivs TEST CONN:
IN DW
-10 C
2 Vivs 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 RETURN 3-301-93 C
CRD RETURN 3-301-96 C
CRD RETURN l
3-301-97 C
CRD RETURN 367 X-121 527-6 283 1"
3-4741-20B C
DW PNEUMATIC SYSTEM l
3-1601-48 0
2" A0-3-4722 C
Top Test Conn.
C 3-4741-20C 0
(VENT) R210VE CAP 367 X-1390 536-6 280 1"
A0-3-4720 C
DW PNEUMATIC SYSTEM k"
Test Conn.
C A0-3-4721 C
3-4771-500 0
VENT PATH 3-4771-501 0
368 X-120 527-6 280 1"
3-4640-500 C
SERVICE AIR 4"
0 VENT VALVE OFF OF LINE
- 8 '#-4" APPROVED 43 of 77 MAR 22 '83 D. 0. S. R.
DTS 1600-7 Revision 6 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 YENT SERVICE ON 517' LEVEL WEST Service Air Top just inside the Sludge Tank Rm.
0 C
VALVE ON LINE 3-4609-A4 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" 3-2301-16 C
TEST CONN.
3-2301-17 C
MO-3-2301-35 C
16" MO-3-2301-36 C
3/4" 3-2301-93 C
DRAIN i
3-2301-94 C
l 374' 1"
S0-3-2301-31 0
50-3-2301-29 C
S0-3-2301-30 C
3-2301-43 C
TEST CONN.
l 3-2301-44 C
374 X-132C 542-6 160 3/4" 3-2301-24 0
HPCI INSTR X-1329 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" S0-3-2 01-32 C
3-2301-50 0
UmARKED BYPASS VALVE 3-2301-74 0
AROUND 3-2301-33 AND M0-3-2301-14 C
3-2301-47 BXR 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 l
3-2599-16B C
ACAD l
1" A0-3-2599-4A C
ACAD wa22 %
44 of 77 D.O.S.R.
DTS 1600-7 Revision 6 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 A0-3-2599-4B C
ACAD of 2 A0-3-2599-5B C
ACAD 146 541 105 3-2599-25A 0
ACAD A0-3-2599-2A C
ACAD 1408 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 1"
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 3-2599-12B C
ACAD 316B 504 280 1"
A0-3-2599-38 C
ACAD 3/4" 3-2599-138 C
ACAD 3-2599-14B C
ACAD 146 541 105 1/2" S0-3-2499-2A C
CM S0-3-2499-1A C
CAM 1/2" 3-2499-7A C
CAM 1/2" 3-2499-BA C
CAM L
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" S0-3-2499-28 C
CAM S0-3-2499-1B C
CAM 1/2" 3-2499-7B C
CAM 1/2" 3-2499-8B C
CAM 315E Torus 305* 1/2" 50-3-2499-48 C
CAM S0-3-2499-3B C
CAM 1/2" 3-2199-10B C
CAM 1/2" 3-2199-98 C
CAM 1
APPROVED 45 of 77 D. O. S. R.
DTS 1600-7 Revision 6 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 capressor OUT-OF-SERVICE and then disconnect and vent the low suction pressure switch trip sensing line to atnosphere.
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).
l Verified l
5.
Remove existing temperature sensor from the 2(3)-1045 A & B well then insert volumetric RTD's in A & B loop (SDC pump room).
Verified l
B.
Test Requirements l
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 l
1.
Disconnect and remove all ILRT temporary instrumentation.
Verified 2.
Conaect the "A ' Pumpback air compressor low suction pressure switch trip sensing line and clear the system outage.
Verified MR 22 '8?
46 of 77 D.O. S. R.
DTS 1600-7 Revision 6 3.
Calibrate the following pressure sensors after completion of the test.
PS-3-1621A OS-3-1632A PS-1601-62A PS-3-1628A PS-3-16218 PS-3-1632S PS-1501-623 PS-3-16288 PS-3-1621C PS-3-1632C PS-1501-62C PS-3-1629A PS-3-16210 PS-3-1632D PS-1501-62D PS-3-16298 Verified 4.
Remove the cable from 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 I
O
.mg l
47 of 77 D. O. S. R.
DTS 1600-7 Revision 6 TECHNICAL STAFF
(
"HECKLIST 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 used in detamining 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 determining the placement of the humidity indicators so that a representative sampling of the primary containment air can be made.
Verified l
h0TE l
As in the case of the temperature survey, this humidity 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 fran the surveys in steps 2 and.3 above.
1 Varified 5.
Obtain the instrument accuracies for all instruments and read-out devices to be used in tys ILRT.
Perfom an error analysis to verify that the accuracy of the collected data is consistent i
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.)
M22M 48 of 77 0.0.S.R.
y
.,e-. - -
- - - - - - - - - - - - - ^ - -
.~
DTS 1600-7 Revision 6 INTERPRETATION f.
Specifically, the combined instr-ument repeatability error should be less than 25% of La, the maximum allowable leak rate.
Verified 6.
Arrange for the availability of the air compressors for use in pressurizing the contaiment.
e Verified 7.
Examine LLRT results for all tests and ve.-ify 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 cpening the seal). This infonnation will be required when the results of the ILRT are analyzed.
Verified 8.
Arrange with the Instrument Mechanics for placemen 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 wi'l indicate gross barometric variations for correlation to test results.
Verified i
10.
Detennine 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 __
l 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.
M Verified 12.
... gg Conduct a thorough examination of the drywell and pressure D.O. S. R.
49 of 77
DTS 1600-7 Revision 6 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.
Verified 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.
\\*erified 15.
Direct the Operations Department in the pressurizing af 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 i
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 MIR22 M Floor Dr Sump Level inches O.O.S.R.
so of 77
DTS 1600-7 Revision 6 B.
Post Test Requirements r
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 the following pressure switches have been calibrated after completion of the test PS-3-1621N PS-3-1621B PS-3-1621C PS-3-1621D PS-3-1632A PS-3-1632S PS-3-1632C PS-3-16320 PS-3-1501-62A PS-3-1501-62B PS-3-1501-62C PS-3-1501-620 PS-3-1628A PS-3-16288 PS-3-1629A PS-3-16298 O
Verified RADIATION PROTECTION CHECKLIST 6 1.
Prior to any venting of the primary containment, an air sample must be taken for analysis.
Verified l
APPROVED NR 22 *83 51 of 77 D. O. S. R.
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.-e
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D I
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)
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(
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C A
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)
O7F P
W
(
ED TN I
)
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(
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't G N
nN I
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(
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(
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9]3
&V g
jas d g h A*
,.ms, DTS 1600-7 O
N Revision s U)
M m d DATA SHEET 2 DATE
~
DATA TABULATION UNIT AVERAGE MBIENT MBIENT REACTOR REACTOR TORUS MBIENT MBIENT RELATIVE RELATIVE WATER WATER WATER SUPERIMPOSED MR TEMPERATURE PRESSURE HUMIDITY HUMIDITY TEMPERATURE LEVEL (In LEVEL (In LEAK RATE
(*F)
(psta)
(%)
(1)
(*F) above 0")
above 0")
(SCFM) i l
W' i
i I
-l 55 of 77
6 NO i6 I
T 0n A
0o C
6i O
1 s L
i Sv Te DR E
T T
I A
N 5
D U
NO I
TACO L
)
F
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4 I
D N
A O
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R TA R
C O
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L NN OE 3I S T
TAE ELR 7
EUU 7
3 HBT SAA 3
f TR f,
A E
N o
TAP O
6 ATM I
DAE T
5 DT A
C G
O N
L I
D L
I UB RO 2
TC N
A O
E I
R TA CO L.
1 NO I
TACO L
S W
R 0
h Nw 5g 0
l 0
l 9O*g*g-1I t
i l
1
6
- 8 G
?*
g; 88 r*5 Eum
- o, W
e M>
^
wE
>= A W
W E.=
W 4
3 C
2 W
Ew WE EZ k
mW W
.K 4
.v-E en J
.K >= w.
C3 E
==
W E
b
- =
WO w-N WW k
yE o
w E d N
R m
<E C-m W
e C
EEM W
L m.= -
W sn
]
JCCL 5=~
=v W
v W
XW E
NNWE^
am-vNN W C3.
>= E w EA EA li
~ MD13 i
p,0.S.R,
,I
\\
g1'
~
i
'/ 6 T
0n I
1 0o M
3i I
P 1 s L
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T Sv EY T e CA N
DR ND R
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D1 I
FT NW S
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DTS 1600-7 Revision 6 APPENLi!X A A.
INSTRUMENT ACCURACY ERROR ANALYSIS Per Topical Report BN-TOP-1 the measured total time leak rate (M) in weight percent per day is computed using the A6 solute Method by the fomula
~
T7 M=(100)f 1-1 where:
T = P -PV = total containment atmosphere absolute pressure, y
y y
in psia, at the start of test, corrected for water vapor pressure.
F = P,-PY = total containment atmosphere absolute pressure, n
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
=
y n
at the start and at data point n, respectively.
li test interval in hours between time 1 and time n.
=
R gas constant.
=
The change or uncertainty interval in M due to uncertainties in the measured variables is given by:
~
i M
= 2400
[dM 3P
'dM 3P 2
4 H
(dP,.
7 1
(2)
O N
T }
I dM T
dM 1
+
2 where S is the standa-d error for each variable. This fonnula assumes that all errors are systematic rather than random in character.
Even though the formula is deteministic it does, however, allow assessment of figure of merit foa various equip-ment to be used in the measuring system without the need for assembling and calibrating the system as an entity.
APPROV!!D
~
15R 22113
" # 77 D,0 S,R,
~
DTS 1600-7 Revision 6 The error in M after differentiating is:
JT T
e\\r J 21 ep 2400 1
p
'M
- H l
~
)
\\p2T 2
1 2 2
e7
+
'T
+
where:
e
=6 P
1 1
e
= 3'2 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:
1 2=
where i is the average volume weighted primary T
=T containment air temperature (*R) during the test; Pg=P2 where P is the total containment atmospheric pressure (psia);
PV1 = PV2 where PV is the partial pressure of water vapor in the primary containment; Equation (3) becomes:
e e
'M 00 2(2) +2(d)
=
E i
l
~
APPROVED 60 of 77 D.O.S.R.
DTS 1600-7 Revision 6 where:
'k e
= the error in pressure which accounts for the p
error in the total pressure measurement system; both total absolute pressure and water vapor pres sure.
(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 / vna. Inst. = error in T
temperature, 'R.
w s
APPROVFD M22 E 6
77 0.0.S.R.
l l
s
DTS 1600-7 Revision 6 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' { E ) 2400 [3,
)
g where L = primary containment leak rate (wt%/ day)
H = time interval between dau sets #1 & #2 (hours)
W1 = weight of the contained dr y air mass at test data set #1 (lbs)
W2 = weight of p.-imary containment temperature at test data set #2 (1bs)
T = volume weighed primary containment tem-1 perature at test data set #1
(*R)
T2 = v lume weighed primary containment tem-perature at test data set #2
(*R)
P = dry air absolute pressure at test data 1
set #1 (psia)
P = dry air absolute pressure at test data 2
set #2 (psia) 7' The standard variation on L due to the uncertainties in the mea-sured variables is given by:
v 3(L) =
[ (h S(P )) +(
(P)) +(
(T)) *I II)) 3 g
I 2
I 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 /> al T,
P2 1
8 P, *T P,' *f I
al T.
-1
$ " ~N I
g =- p -g assuming P=P 7 and T = T = T 7
2 g
2 where 7 = average absolute dry air pressure (psia)
T = average volume weighed primary containment absolute temperature (*R)
Therefore, APPROVED WR2213 62 of 77 D.O.S R,
DTS 1600-7 Revision 6
{
&(L) = 100[2( I } )' + 2(IIT) )*]b 7
7 1.
Calculation of &(T)
NVOL T = I(VF)) (Tave,y) j=1 where VF) = the volume weighing factors NVOL = the number of containment subvolumes Tave ) = the average absolute temperature in the jg subvolume N
Tave, =
where Ti,j = the absolute temperature of the 12 RTD in the jg
<~
Nj = number of RTD's in the je subvolume Now, &(T) is calculated from NVOL g7
&(T) = jf Stave j (Tave,j) where
= VFj 6Tav O(Tave.j) = m accuracy (N )%
j Therefore, 4(T) =
(Vfj) (m ace acy) g 2.
Calculation of d(7) d(F) = [d(P ) +d(P)*]b T
y where PT = total absolute primary containment pressure APPROVED Py = containmentpartial pressure of water vapor in the primary s
MAR 22 '33 83 f 77 D. O. S. R.
~
DTS 1600-7 Revision 6 PG accuracy substituting 8(PT) =
{
(f of PPG's)5 NVOL 8(PV) = 1 (VFJ) (dewcell accuracy) j=1 (Nj)5 where PPG = precision pressure gage NJ = number of dewcells in the jg subvolume Therefore, 2
WR 2
8(7) = [( GaecQ,e ) +(I (VFj) (dewcell accuracyg )h of j=1 (Nj) 3.
Detemine the appropriate variable quantities and perfom the above analysis twice - once for the systen accuracy and once for the systen repeatability.
r.
t 1
l
(,
ARPRover) 64 of 77 l
D. O. S..,
....aa
.,._a
_._2
__a 4._._._
y
~
DTS 1600-7 Revision 6 APPENDIX C CALCULATIONS PERFORMED Data collected from pressure sensors, dewcells, and RTD's located in the containment are processed using the following calculations for containment temperature and dry air pressure.
A.
Average Subvalume Temperature and Dewpoint.
Tj = I(al'i RTD's in JSsubvolume)
.F (1)
Number of RTD's in the ja subvolume D*Plj = I(all deweell in j$ subvolume)
- F (2)
Humber of dewcells in j2 subvolume where Tj = average temperature of the j2 subvolume D.P.j = average dewpoint of the J M subvolume NOTE By definition D.P.j 5 Tj) 8.
Primary Containment Tamparature and Dry Air Pressure I
L NVOL If Tj = undefined, then l
T=
I (VFj) (Tj) *F (3)
Tj = T (j + 1) for is js(NVOL-2) l 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 isjs(NVOL-2) j=1 D.P.j = D.P. (j - 1) for j = NOVL-1 D.P.j = estimate, for j = NVOL D.P.('K) = 273.16 + 0.P X = 647.27 - D.P. ('K) 8 1
EXPON = X(A + ZX + CX3)
A = 3.2437814 (D.P. (
- K))(1+DX)
Z = 5.86826.10
py, (218.167) (14.696)
PSI C = 1.702379.10-0
,(EXPON in 10)
D
- 2.1878462.10' p, I(All absolute pressure gauges)
PV Psia (5)
Number of absolute pressure gauges where:
NVOL = number of primary containment subvolumes VFj a volume weighing factor of the jg subvolume T = volume weighed containment temperature D.P. = volume weighed containment dewpoint X.A,Z,C D.EXPON = dewpoint to vapor pressure conversion
%PPROVED constants a coefftetents l
MR 22 '83
" # 7' D.O. S.R.
DTS 1600-7 Revision 6 Py = volume weighed containment vapor pressure P = contained dry air absolute pressure NOTE The subvolume numbering sequence is from the wannest to the coolest subvolume.
(Assuming top to bot-tom due to stratification.)
l l
i APPRDVED MAR 22 '83 66 of 77 D.'O. S. R.
DTS 1600-7 Revision 6 APPENDIX 0
(
CALCULATIONS PERFORME9 FOR IPCLRT DATA FOR TEST DURATION AT LEAST 12 HOURS Data collected from pressure sensors, dew cells, and RTD's located in the i
containment are processed using the following equations. Some data needs to be analyzed using equations in Ap.oendix 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-L Rev.1. Section 4.5 the following equation is given for the measured lesk rate using the total time procedure:
T7
- i. E (1-
)
(%perday)
M H
TPio where M g n>6asured leak rate in weight % per day for
=
th the i data point.
H time interval, in hours, between musurements.
=
f T,, T4 mean absolute tenperature. *2, of the containmer.t
=
atmosphere et the beginning and the end of test interval (H) respectively.
P,,
Pg mean total absolute pressure, psia, of the
=
containment atmosphere at the beginning and and of the test interval (H) respectively.
Using the following relationship derived in ANSI N45.4 - 1972
. Appendix 3 given below:
T, 7 oW1 9
=1-T P, W
j l
o where W,, Wg = dry air mass of the containment at the beginning of the test and data point 1, 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 (y,3,,,,(LEVELi - 50)(28.635)))
M 2400 9
(3, T P, (volume - (LEVEL, - 50)(28.635))
l 4
1,PPROVED l
.3,,, trygt,, trygtj.,,,cto,,,t,,i,y,i in inc3,,,e 3,93nn$ng i
of the test and the data point i, respectively.
MAR 22 '83 67 of 77 D.O.S.R.
DTS 1600-7 Revision 6 B.
CALCULATED LEAK RATE
('
The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured da ta. The criterion for the best fitting line to a set of data points is that the sisn 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 mass 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 frm the ideal straight line situation.
' Based on this statistical process, the calculated leak rate is obtained from the equation:
L9=A
+B xt g 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 g, [nI(t )(M )] - [(I i)(I 4)]
t M
9 i
[n I(t )3 - (st )3]
j 9
IMi
- Bft, A=
In order to reduce the round-off error in the above calculations, l
the equations are rearranged such that:
tM t
"I 9 9, (g 9 3(gM )
9 B=
nI(t )z - (It,12 g
,, (I 1)(I 1*) - (I i)(I i i>
M t
t tM nit,z - (It ):
9 l
l APPROVED MIR 22 '83 D. O. S. R.
68 of 77 l
t
~
DTS 1600-7 Revision 6 C.
95% CONFIDENCE LIMITS To deterrrine the value of the confidence limits the following statistical infomation is required; the variance, standard deviation, and students' T-distribution.
52 = 550 n-2 where SSQ =
(M - L )2 g
52 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. Additionally, it can be shown 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 detemined using a statistical table called a " Table of Percentage e
Points of the T-Distribution" and provide increased confidence in l
outcomes for small and large sample sizes.
l The Table of T-Distributions 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:
a = S2 [1+1+
3 2
"~
n I(tj - t)2 a=S
[1+1+
D~
3 l
n 1(t - t):
j l g APPROVED WR 22 '83 69 of 77 D.O.S.R.
1 l
l
DTS 1600-7 Revision 6
- * ' ' t
- time after start of tegg g
l'~
t. It, n
UCL = L, + TD x a I
- (
W WR22 W 70 of 77 D.O.S.R.
DTS 1600-7 Revision 6 APPENDIX E CALCULATIONS PERFORMED FOR IPCLRT DATA FOR TEST DURATION AT LEAST 24 HOURS Data co11 acted from pressure sensors, dew cells, and RTO's located in the contcinment are processed using the following equations.
Some data needs to be analyzed using equations in Appendix C prior to use of these i
equations.
l A.
Contained Dry Air Mass.
W = (28.97)(144)(P)[(volume) - (LEVEL-50)(28.635)] lbs.
1545.33 (T + 453.69)
LEVEL = reactor water level in inches from instrument zero
(
(28.635 ft/in)
Volume = primary containment volume (ft) with:
Rx level 9 50.0 inches, Torus level 9 - 3.0 inches.
B.
MeasurM Leak Rates.
Lm(TOTAL) = " Base Ni 2400
-t W
Day 1
g,3, Base Lm(POINT) = W -1 Ni 2400 i
t
- t -1 W
Day g
j j,3 where, WBASE = mass of contained air at t=0 (1bs)
Wj = mass of centained air at t=1 hrs (lbs) tg - test duration at the 1,th, data set (hrs)
C.
Statistical Leak Rate and Confidence Limits.
LINEAR LEAST SQUARES 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 fittir.g line to a set of data points is that the sum of the squares of the deviations of the observed points fr am 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 ' lot of the measured contained dry air mass versus time would p
ideally yield a straight lina 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 71 of 77 D. O. S. R.
,,,,-._..,,,,n-
,...e
-~~ --
DTS 1600-7 Revision 6 Based on this statistical process, the calculated leak rate is
(
obtained from the equation:
W = At + B dhere W = contained dry air mass at tiine t (lbs)
B = calculated contained dry air mass at time t= 0 (1bs)
A = calculated leak rate (1bs/hr) t = test duration (hours)
Contained Dry Air Mass (1bs)
%pg 4
Test Duration (nrs)
The values of the constants A and B such that the regression line is best fitting to the ILRT data are 3, [NR ti) (Will - [ Tti) TWi)3
[Ng ti)' -
Eti)2 j B = IWi - AIti N
i In order to reduce the round-off error in the above calculations, the equations are rearranged such that:
p, I:(ti-Y (WJi E J(ti-t)'J B = M(ti)2)(::Wi)] - [(Iti)(I(ti)(Wi))]
LTI(ti)'
(Iti)*J l
By definition, leakage out of the primary containment is considered positive leakage; therefore, the statistically average leak rate in weight percent per day is given by:
Ls = (-A)(2400)/B (weight %/ day)
Statistical Uncertainties
~oPROVED In order to calculate the 95% confidence limits of the statistically MAR 22 '83 72 of 77 D. O. S. R.
1 l
.e DTS 1600-7 Revision 6 average leak rate, the standard deviation of the least squares slope and the Student's T-Distribution function are used as follow:
NZ 2
E (Wi)2-CWi?2
'" [TiRT NI(t'iji-(Iti? ' ^ 3p 1
UCL = L + a(TE)(2400) 5 B
whereTE=1.645+I*f,0 7 6
(
N = number of data sets ti = test duration of the ith data set Wi = contained dry air mass 7t the 12 data set 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 l
l APPROVED M 22 *S3 73 of 77 D. O. S. R.
t a.
DTS 1600-7 Revision 6
. APPENDIX F IPCLRT DEFINITIONS g
(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
= 192.644 SCFH 14.696
= 821.857 SCFH Maximum Allowable Operation Leakage Rate (L )
t L = 75% of Maximum Allowable Leakage Rate t
= (0.75) (821.857) SCFH E
= 616.392 SCFH
. Maximum Allowahle Leakage for any One Main Steen Isolation Valve
'2 11.5 SCFH 9 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 Leakage Rate of the personnel interlock door is 3.75 percent of La.
(3.75%) (821.857) = 30.820 SCFH
[
APPROVED e
IIIR 22 M 74 of 77 D.O. S. R.
V
~
DTS 1600-7 m,.
Revision 6 TABLE I
{
List of Non-Vented Systems SYSTEM NO.
PENETRATION NO LEAK RATE (SCFH) 220-57A & 220-55A X-107B 220-57A & 220-62A X-107B 220-57B & 220-58B X-107A 220-578 & 220-628 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-NA & 25A X-149B f
1402-48,8B,258 & 36B X-310B 1402-248 & 258 X-149A 1501-18A & 19A X-311A 1501-188 & 19B X-311B 1501-20A & 1501-38A X-310A 1E01-208 & 1501-388 X-310B 1501 22A,26A & 1001-5A X-116A 1501-25A & 1501-26A X-116A 1501-22B,26B & 1001-5B X-1168 1501-258 & 1501-26B X-116B 1501-27A & 1501-28A X-145 1501-27B & 1501-288 X-150A 2301-45 & 2301-74 X-317 1
APPROVED MAR 22 '83 75 of 77 D.O. S. R.
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y,-
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FIGURE 1 DTS 1600-7 R3 vision 6
.s.
$UGGESTED -
t" '
r h
~
s Mo-2-1501-28A Mo-2-1501-27A (Mo-3-1501-183)
(Mo-3-1501-273)
Drosell Containment Spray Header
~
2(3)-1504-10" 7K nr as nr
^\\
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Orpsell Penetration Test Connection l
Flange gn -
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VErrr s
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blRCOMP
~~
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~
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APPROVED
=
u
.. a 77'of.' 77 (FINALt
.