ML20082H143
| ML20082H143 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Cook |
| Issue date: | 04/02/1980 |
| From: | Litwinski C INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML20082H066 | List: |
| References | |
| FOIA-83-384 12THP-4030-STP., NUDOCS 8312010036 | |
| Download: ML20082H143 (150) | |
Text
i g
l INDIANA 6. MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET liEFERENCE COPY ON!.Y
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NO REVI5!ONS TO BE ISSUED Revision No.
3 TITLE CONTAIN!!ENT INTEGRATED LEAK RATE SURVEILLANCE TEST SCOPE OF REVISION Rev.1 - Changed procedure famat, changed Purpose and Acceptance Criteria to conform with Technical Specifications, revised valve list.
Rev. 2 - Revised to make applicable to both Unit I and Unit 2 and expanded to make more comprehensive and to reflect new test requirements.
No marginal markings used.
Rev. 3 - Incorporated Temporary Sheets 1, 2, 3, 4, 5, 6, 7, 9, 12.
(Original Cover Sheet Lost)
SIGNATURES ORIGINAL Rev.I REV.2 Rev.3
.}i o t PREPARED BY E. Kant D. Engle g
pg n
ASS CE R. Keith R. Keith
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y INTERFACING DEPARTMENT
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HEAD CONCURRENCE N/A N/A
}jg DEPARTMENT HEAD APPROVAL T. Plunkett T. Plunkett PLANT NUCLEAR SAFETY COMMITTEr D. Shaller D. Shaller //
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gm 3fg y R. Jurgensen R. Jurgensen NAGER DATE OF ISSUE l-13-75 6-15-76 g g.'/ g' y, y,g
~ )13 d3 8312010036 830825 PDR FOIA COGOLB3-384 PDR ron. No. PMl 2010 REY. :
INDIANA 6. MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT
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PROCEDURE COVER SHEET Procedure No. **~1 THP 4030, STP.202 Revision No.
T4TLE CONTAINMENT INTEGRATED LEAKAGE TESTS SURVEILLANCE TEST
~ SCOPE OF REVISION Rev. #1:
Changed procedure form t, chanced Purpose and Acce Criteria to conform with Technical Specifications,ptance revised valve list.
= _ _. _ _.
bbibOE[$E 00EY $.kV
'NO REVi5;005 TO BE ISSUED SIGNATURES ORIGIN E Rev.I REV.2 Rev.3 1,,
n
.r PREPARED BY
-h}/
M 8.
QUALITY ASSURANCE" h
c$
REVIEW l
l INTERFACING DEPARTMENT l
HEAD CCNCURRENCE N. A -
NA DEPARTMENT HEAD Jg M fp[ Q APPROVAL
(([,g PLANT NUCLEAR
,M SAFETY COMMITTEE If/
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AEPSC NUCLEAR SAFETY &
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DESIGN REVIEW COMMITTEE g[M d/, M,
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PLANT MANAGER A')p{4 Arraava n
DAT" CF ISSUE l-13 7.-f
-5 76 Ferm !!c. P!c 2010-1_ Rev.1
5
- 12 THP 4030 STP.202 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE 1
Rev. 2 - May 16,1978 2
Rev. 2 - May 16, 1978 3
Rev. 2 - May 16, 1978 4
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Rev. 2 - May 16, 1978 5
Rev. 3 - April 2,1980 6
R'ev. 3 - April 2,1980 7
Rev. 2 - May 16,1978 8
Rev. 3 - April 2,1980 9
Rev. 2 - May 16, 1978 10 Rev. 2 - May 16,1978 11 Rev. 2 - May 16,1978 12 Rev. 2 - May 16,1978 I
13 Rev. 2 - May 16, 1978 14 Rev. 3 - April 2,1980 15 Rev. 3 - April 2,1980 i
16 Rev. 3 - April 2,1980 17 Rev. 3 - April 2,1980 18 Rev. 2 - May 16, 1978 Index of Appendices - Page 1 of 1 Rev. 3 - April 2,1980 Appendix A - Page 1 of 3 Rev. 2 - May 16, 1978 Appendix A - Page 2 of 3 Rev. 2 - May 16, 1978 Appendix A - Page 3 of 3 Rev. 2 - May 16,1978 Appendix B.1 - Page 1 of 3 Rev. 3 - April 2,1980 Appendix B.1 - Page 2 of 3 Rev. 3 - April 2,1980 Appendix B.1 - Page 3 of 3 Rev. 3 - April 2,1980 Appendix B.2 - Page 1 of 1 Rev. 2 - May 16, 1978 Page 1 of 4 Rev. 3 4/2/80
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- 12 THP 4030 STP.202 List of Effective Pages (Can't)
PAGE NUMBER REVISION NUMBER AND DATE Appendix B.3 - Page 1 of 2 Rev. 2 - May 16, 1978 Appendix 8.3 - Page 2 of 2 Rev. 2 - May 16, 1978 Appendix B.4 - Page 1 of 2 Rev. 2 - May 16, 1978 Appendix B.4 - Page 2 of 2 Rev. 2 - May 16, 1978 Appendix B.5 - Page 1 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 2 of 26 Rev. 2 - May 16,1978 Appendix B.5 - Page 3 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 4 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 5 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 6 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 7 of 26 Rev. 2 - 11ay 16,1978 Appendix B.5 - Page 8 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 9 of 26 Rev. 2 - May 16, 1978 t
Appendix B.5 - Page 10 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 11 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page/12 of 26 Rev. 2 - May 16, 1978 Appendix 8.5 - Page 13 of 26 Rev. 2 - May 16, 1978 l
Appendix 8.5 - Page 14 of 26 Rev. 2 - May 16,1978 Appendix 8.5 - Page 15 of 26 Rev. 2 - May 16,1978 l
Appendix 3.5 - Page 16 of 26 Rev. 2 - May 16, 1978 t
i Appendix B.5 - Page 17 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 18 of 26 Rev. 3 - April 2,1980 l
Appendix 8.5 - Page 19 of 26 Rev. 3 - April 2,1980 l
Appendix B.5 - Page 20 of 26 Rev. 3 - April 2,1980 Appendix B.5 - Page 21 of 26 Rev. 2 - May 16,1978 Appendix B.5 - Page 22 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 23 of 26 Rev. 2 - May 16, 1978 Page 2 of 4 Rev. 3 4/2/80
- 12 THP 4030 STP.202 List of Effective Pages (Con't)
PAGE NUMBER REVISION NUMBER AND DATE Appendix B.5 - Page 24 of 26 Rev. 2 - May 16, 1978 Appendix B.5 - Page 25 of 26 Rev. 3 - April 2,1980 Appendix B.5 - Page 26 of 26 Rev. 2 - May 16, 1978 Appendix C.1 - Page 1 of 2 Rev. 2 - May 16, 1978 Appendix C.1 - Page 2 of 2 Rev. 2 - May 16, 1978 Appendix C.2 - Page 1 of 2 Rev. 2 - May 16, 1978 Appendix C.2 - Page 2 of 2 Rev. 2 - May 16, 1978 Appendix D.1 - Page 1 of 3 Rev. 3 - April.2,_1980 Appendix D.1 - Page 2 of 3 Rev. 3 - April 2,1980 Appendix D.1 - Page 3 of 3 Rev. 3 - April 2,1980 Appendix D.2 - Page 1 of 5 Rev. 2 - May 16,1978 Appendix D.2 - Page 2 of 5 Rev. 2 - May 16, 1978 Appendix D.2 - Page 3 of 5 Rev. 2 - May 16,1978 e
Appendix 0.2 - Page 4 of 5 Rev. 2 - May 16,1978 Appendix D.2 - Page 5 of 5 Rev. 2 - May 16, 1978 Appendix D.3 - Page 1 of 10 Rev. 2 - May 16, 1978
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Appendix D.3 - Page 2 of 10 Rev. 2 - May 16,1978 Appendix D.3 - Page 3 of 10 Rev. 2 - May 16, 1978 Appendix D.3 - Page 4 of 10 Rev. 2 - May 16, 1978 l
Appendix D.3 - Page 5 of 10 Rev. 2 - May 16, 1978
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Appendix D.3 - Page 6 of 10 Rev. 2 - May 16, 1978 Appendix D.3 - Page 7 of 10 Rev. 3 - April 2,1980 Appendix D.3 - Page 8 of 10 Rev. 2 - May 16, 1978 Appendix D.3 - Page 9 of 10 Rev. 2 - May 16, 1978 Appendix 0.3 - Page 10 of 10 Rev. 2 - May 16, 1978 Appendix D.4 - Page 1 of 1
, Rev. 3 - April 2,1980 Appendix E - Page 1 of 1 Rev. 2 - May 16, 1978 Appendix E.1 - Page 1 of 1 Rev. 2 - May 16, 1978 Page 3 of 4 Rev. 3 4/2/80
- 12 THP 4030 STP.202 LIST OF EFFECTIVE PAGES, Cont'd.
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Page Number Revision Number and Date Appendix E.2 - Data Sheet 1 Rev. 2 - May 16,1978 Appendix E.2 - Data Sheet 2 Rev. 2 - May 16,1978 Appendix E.2 - Data Shest 3 Rev. 2 - May 16,1978 Appendix E.2 - Data Sheet 4 Rev. 2 - May 16,1978 Appendix E.3 - Data Sheet 1 Rev. 2 - May 16,1978 Appendix E.3 - Data Sheet 2 Rev. 2 - tiay 16,1978 Appendix E.3 - Data Sheet 3 Rev. 2 - May 16,1978 Appendix E.3 - Data Sheet 4 Rev. 2 - May 16,1978 Appendix E.4 - Data Sheet 1 Rev. 2 - May 16,1978 Appendix E.4 - Data Sheet 2 Rev. 2 - May 16,1978 Appendix E.4 - Data Sheet 3 Rev. 2 - May 16,1978 Appendix E.4 - Data Sheet 4 Rev. 2 - tiay 16,1978 Appendix E.5 - Data Sheet 1 Rev. 2 - May 16,1978 Appendix E.5 - Data Sheet 2 Rev. 2 - May 16,1978 Appendix E.5 - Data Sheet 3 Rev. 2 - May 16,1978 Appendix E.5 - Data Sheet 4 Rev. 2 - May 16,1978 Appendix E.5 - Data Sheet 5 Rev. 2 - May 16, 1978 Appendix F - Page 1 Rev. 2 - May 16, 1978 Appendix F - Page 2 Rev. 2 - tiay 16,1978 Page 4 of 4 Rev. 2 - 5/16/78
- 12 THP 4030 STP.202 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT CONTAINMENT INTEGRATED LEAK RATE SURVEILLANCE TEST 1.0 PURPOSE 1.1 The purpose of this procedure is to demonstrate the reactor containment leakages according to the following Unit 1 and Unit 2 surveillance requirements.
4.6.1.2 The containment l'eakage rates shall be demonstrated l
at the following test schedule and shall be determined i
in confomance with the criteria specified in l
Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
l a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40+10 month intervals during shutdown at P, 12 psTg, during each 10-year service period. $hethirdtestof each set shall be conducted during the shutdown for the 10-year plant inser< ice inspection.
b.
If any periodic Type A test fails to meet.75 La, the test schedule for subsequent' Type A tests shall be reviewed and approved by the Comission.
If two consecutive Type A tests i
fail to meet.75 La, a Type A test shall be performed at i
ienst, every is montns untii two cuasecutive Type A test:-
meet.~75' La, at which~ time ^ the above1est schedulev.ay be 7esumed.
c.
The accuracy of each Type A test shall be ver1tled
'by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La-2.'
Has a duration sufficient to establish accurately the change in leakage rate between the Type A l
test'and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured at Pa, 12.0 psig.
f.
All test leakage rates shall be calculated using observed data converted to absolute values. Error analysis shall be performed to select a balanced integrated leakage measurement system.
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Rev. 2 5/16/78 L
- 12 THP 4030 STP 202
2.0 REFERENCES
2.1 Unit 1 Technical Specifications 2.2 Unit 2 Technical Specifications 2.3 Unit 2 FSAR Amendment 78 Appendix Q Question 022.14 2.4 American National Standard - ANSI, N45,4-1972 Leakage Rate Testing of Containment Structures for Nuclear Reactors.
r 2.5 Code of Federal Regulations (See Appendix A of this procedure) 10 CFR 50; Appendix J Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
2.6 System Description SD-DCC-HP117 Compressed Air System 2.7 Operating Procedure OHP 4021.064.005, Placing Containment Pressure Test Air Dryer In and Out of Service.
2.8 D.C. Cook Nuclear Plant Mechanical Drawings.
2.8.1 RTD Locations for Integrated Leakage Rate Test Dwg. No. 1-2-5611.
l 2.8.2 Instrument Piping - Instrument Room Dwg.
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No. 1-5581, 2-5581.
2.8.3 Instrument Piping - Instrument Room Dwg.
No.1-5581 A, 2-5581 A.
2.8.4 Instrument Piping - Instrument Room Dwg. No.
1-55818, 2-55818.
2.8.5 Instrument Piping - Instrument Room Dwg. No.
l l-5581C, 2-5581C.
l 2.8.6 Arrgt. and Details Computer Room Carrier Racks
" Car 1 and 2" and Miscellaneous Panels.
Dwg. No. 1-2-5553.
2.9 D. C. Cook Nuclear Plant - Electrical Drawings 2.9.1 Containment Hemidity Detector - Elementary Diagram Dwg. No. 1-98306, 2-98306.
2.9.2 Containment Humidity Detectors Cabinet "CHD" Dwg. No. 1-91035, 2-91035.
2.9.3 Containment Humidity Detector Console
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Wiring Diagram Dwg. No. 1-97464, 2-97464.
Page 2 Rev. 2 - 5/16/78 l
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- 12 THP 4030 STP.202 2.9.4 Containment Humidity Detector Console
" Spare" Wiring Diagram Dwg. No. 1-97465.
2.9.5 ILRT Test Rack LRT-1, LTR Wiring Diagram Dwg. No. 1-52375, 2-92375.
2.9.6 Containment Temperature and Alam Devices Quad 1 Dwg. No. 1-97441, 2-97441.
2.9.7 Containment Temperature and Alam Devices -
Quad 2 Dwg. No. 1-97444, 2-97444, 2.9.8 Containment Temperature and Alam Devices -
Quad 3 Dwg. No. 1-97447, 2-97447.
2.9.9 Containment Temperature and Alam Devices -
Quad 4 Dwg. No. 1-97450, 2-97450.
2.9.10 Coltrol Penetration 1-4-I-6, 2-4-I-6 ILRT - RTD Penetration Dwg. No. 1-97505, 2-97505 2.9.11 Control Penetration 1-1-I-6, 2-1-I-6 ILRT - RTD Penetration Dwg. No. 1-97515, 2-97$15.
2.9.12 Control Penetration 1-2-I-7, 2-2-I-7 ILRT - RTD Penetration
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Dwg. No. 1-97525, 2-97525 l
2.9.13 Control Penetration 1-3-I-5, 2-3-I-5 ILRT - Dew Point Hygrometer Dwg. No. 1-97535, 2-97535 2.9.14 Auxiliary Relay Racks Remote Front View LTR-1 or LTR-2 Arrangement Dwg. No. 1-91053 2.9.15 Auxiliary Bldg. Temp. and Alam Devices 1
ILRT - Dew Point Hygrometer Local Readout Dwg. No. 1-95342, 2-95342 l
2.10 Vendor Manuals 2.10.1 Mensor Quartz Manometer Operating Instructions 2.10.2 Cambridge Sy tems Industrial Dew Point Hygrometer Instruction Manual - Models 660 & 992.
2.10.3 Hy-Cal Engineering l
Operation and Maintenance Manual l
Modular Bridge Amplifier System Model ESD-9050-A 2.10.4 John Fluke Mfg. Co. Model 2240A data logger i
Page 3 Rev. 2 - 5/16/78 s-
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A 3 -
2.11.4 12-PI-06, " Verification of ILRT Computer Program" 2.12 AEPSC - ILRT Analysis Programs 2.12.1 'ILRTEST' Computer Program 2.12.2 'ILRTEST' Operations Guide 3.0 INITIAL CONDITIONS 3.1 Verify that the following test prerequisites have been satisfied:
3.1.1 The unit for which the ILRT is to be conducted is in Mode 5.
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PERF l
l 3.1.2 The following surveillance test procedures have been satisfactorily completed.
3.1.2.1 1-2-THP 4030 STP.203, " Type B and C Leak Rate Test" 3.1.2.2 1-2-THP 4030 STP.204, " Personnel Air Lock Leakage and Interlock Test"
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PERF 3.1.3 The Plant Air System is available to pressurize the reactor containment.
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OPER 3.1.4 The Plant Air System in conjunction with the Containment Pressurization Test Air Dryer is capable of delivering to the reactor containment instrument quality air dried to a dew point of.1 -20 F.
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PERF 3.1.5 Blind flanges have been removed and the spool piece inserted in the Containment-l Pressurization Test Line (CPN-57).
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MAINT 3.1.6 A hatch in the operating deck has been removed to allow equal pressurization between upper and lower volumes.
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I MAINT Page 4 Rev. 2 - 5/16/78
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- 12 THP 4030 STP.202 3.1.7 A general inspection of accessible interior and exterior surfaces of the containment has been made to uncover any evidence of structural deterioration which may sffect the containment structural integrity or leak-tightness.
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PERF 3.1.8 All containment floor surfaces, including the refueling cavity and canal, are as free of water as possible.
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PERF-3.1.9 The load cell readouts for the polar crane have been removed from the 3
containment.
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C&I 3.1.10 All bottled gas, including N2 and CO2 has been removed from the containment.
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MAINT 3.1.11 The containment ventilation fans are available for recirculation by by-passing the containment isolation phase A and B signals and the NESW low flow interlocks.
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PERF 3.1.12 Instrumentation and control devices that require pressure equalization (see instrument venting list, Appendix B.1) during the Integrated Leakage Rate Test have been equalized by opening vent valves, loosening cover plates and gage glass screws, etc.
C&I l
3.1.13 The Lower Containment Pressure Hi and Hi-Hi signals to Safeguards Actuation and Containment pressurization have been blocked to prevent actuation of the safeguards system.
3.1.13a PPP-300
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C&I 3.1.13b PPP-301
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C&I 3.1.13c PPP-302
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C&I 3.1.13d PPP-303
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C&I 3.1.14 Install the television monitoring system for observing the Loop 3 standpipe for reactor coolant level from the control room, f
C&I Page 5 Rev. 3 4/2/80
- 12 THP 4030 STP.202 3.1.15 Provisions for a temporary drain pot for the ice condenser fan coolers has been provided at drain valve WD-301 (See flow diagram 12-5137A).
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MAINT 3.1.16 The glycol supply to thit 1 ice condenser fan coolers has been aligned to glycol pumps and chillers independent from those aligned to Unit 2.
3.1.16a Verify the proper shutoff valves at the glycol pumps, glycol chillers and glycol supply and return headers have been closed to effectively isolate the Unit 1 and Unit 2 glycol systems from each other.
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OPER 3.1.16h VCR-11 and -21, glycol supply and return isolation valves inside the con-tainment shall be blocked open so as to prevent their closure when control air to the containment is isolated.
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C&I 3.1.16c Block closed the lower ice condenser inlet doors.
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i PERF 3.1.17 Pipe plugs on the Ice Condenser Equipment Access
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Doors have been removed.to pennit pressure equalization.
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MAINT l
3.1.18 A lead from each of the Ice Condenser AHU d/p switches controlling the defrost cycle has been lifted. Operations shall be notified of this so that a manual defrost schedule may be established and implemented.
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C&I l
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Rev. 3 4/2/80 l
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o*12 THP 4030 STP.202 3.1.19 The following sections of piping are to be drained of water. (See sketches Appendix 8.2).
3.1.19a The primary water line between the hose connections used for reactor cavity scrubdown and DW-207 for Unit 1 or DW-208 for Unit 2 (Ref. Dwg. 1-2-5115A).
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OPER 3.1.19b The primary water line to the PRT j
between PW-272 and PW-276 (Ref.
Dwg.1-2-5115A).
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OPER 3.1.19c The containment vent unit drain lines (Ref. 12-5137A).
f OPER 3.1.19d The ice condenser fan cooler unit t
I drain lines (Ref. 12-5137A).
f 3.1.20 The Main Steam Generators are vente to outside atmosphere upstream of the steam generatorstops by opening test connections on MPP-210, -220, -230, and -240.
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C&I i
3.1.21 The following systems or portions of systems are open to containment. (See sketches, Appendix B.3).
3.1.21a Vent Line from Prz. Relief Tk.
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OPER 3.1.21b Reactor Coolant Drain Tk.
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OPER 3.1.21 c Reactor Coolant System (0 pen either reactor vessel head vent or pressurizer vent).
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UPtM 3.1.21d AccumulatorTanks(4).
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OPER 3.1.22 The following pressurized systems, which penetrate the containment, are isolated from the containment and are vented to both containment and outside atmosphere.
(See sketches, Appendix B.4).
l 3.1.22a N2 to Pressurizer Relief Tank.
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OPER 3.1.22b N2 to Reactor Coolant Drain Tank.
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OPER 3.1.22c N2 to Accumulator Tks.
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OPER Page 7 Rev. 2 5/16/78 l
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- 12 THP 4030 STP.202 3.1.22d Service Air to
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Containment.
3.1.22e Containment instrument
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air headers.
The containment penetration 3.1.22f and weld channel pressurization
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system.
__OPER All lines penetrating the containment have their associated isolation valves positioned as 3.1.23 indicated on the " Valve Alignment List"
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(See Appendix B.5).
_ ER OP All containment isolation valves 3.1.23a have been closed by nomal operation, without any preliminary exercising
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or adjustments.
OPER All air operated and motor operated isolation valves required to be closed during the ILFT 3.1.23b closed in the nomal manner.
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OPER RHR shall be lined up for nomal eqoldown.
NOTE:
The valve line-up shall in no manner affect l~
the safe shutdown condition of the plant.
3 Any deviations from the specified valve line-up I
required to maintain the plant in a safe shut-down condition shall be noted on Appendix B.5.
The "Nomal" anJ " Spare" Cambridge Dew 3.1.24 Point Hygrometers have been installed in the containment instrument room with provisions for local readout external to the containment.
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C&1 Sample lines for the lower containment dew 3.1.25 point hygrometers have been isolated from the ventilation ducts and vented to the
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lower containment.
C51 The "Nomal" as well as the " Spare" 3.1.26 hygrometers have been functionally checked as per the checkout procedure found in their respective instruction
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manuals.
The ILRT Air Temperature Monitoring System i
3.1.27 has been installed, wired on the LRT Test
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Panel, and checked for operability. C&I Page 8 Rev. 3 l
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col 2 THP 4030 STP.202 3.1.28 The ILRT pressure measurement devices (Mensor Direct Reading, 0-30 PSIA Quartz Manometers, or their equivalent) have been connected to the test connections provided on the sensing lines for the containment pressure transmitters indicated below.
(See Appendix C.1).
3.1.28a UPPER COMPARTMENT PPP-310 (PU-1)
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C&I PPP-312 (PU-2)
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C&I 3.1.28b LOWER COMPARTMENT PPP-303(PL-1)
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C&I PPP-303 (PL-2)
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C&I 3.1.28c ICE CONDENSER COMPARTMENT PPX-301 (PI-1)
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C&I PPX-301 (PI-2)
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C&I 3.1.29 A 0-30 psig Heise gauge model CPE, or equivalent, has been connected to the provided test connection 'A' on PPP-302.
(See Appendix C2).
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C&I 3.1.30 A flowmeter whose span is approximately 0.6 - 6.0 SCRi (Brooks Model 1110-08 or equivalent) and needle valve have been connected to the provided test connection
'A' on PPP-302 for use during the Supplemental Test. (See Appendix C2).
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C&I 3.1.31 A reliable means of comunications between data takers and the official time keeper has been i
established.
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PERF l
3.1.32 A clock with a minimum accuracy one
'1, minute per day with readings in hours and l
minutes is available at the the time keepers station.
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PERF Page 9 l
Rev. 2 l
5/16/78 l
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- 12 THP 4030 STP.202 3.1.33 A Test Supervisor, Data Takers and an official Time Keeper have been designated before the start of the test.
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PERF 3.2 The following data have been collected and calculations performed.
3.2.1 "The Type C Leakage Penalty Fonn" found in Appendix D.1 has been completed.
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PERF NOTE: The above step sumarizes the valves that are Type C tested but cannot be drained and vented during the conduct of the Type A test.
3.2.2 "The Instrument Calibration and Certification Summary Form" found in Appendix D.2 has been completed.
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PERF 3.2.3 "The Fixed Information Data Coding Fonn" found in l
Appandix D.3 has been completed.
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PERF 3.3 Verify that the following preparations for processing ILRT data have been satisfied.
3.3.1 The Instrument Calibration coefficients, RTD weighting factors, and volume weighting factors determined in Appendix D.3 have been punched on cards per the i
Fixed Information Data Coding Form found in Appendix D.3.
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PERF 3.3.2 The AEPSC Computer Applications Section Head shall l
be notified of the projected test date as early as possible so that top priority for processing the data analysis programs may be secured and he may have supp' rt personnel standing by as he may deem o
necessary.
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PERF 3.3.3 A minimum of 4 operators fully comprehending the operations required I
to process and edit data entered into I
the plant's Data 100 remote tenninal will I
be available for this test.
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PERF NOTE: This step only applicable if a programable on-site j
data analysis system has been secured.
3.3.4 The on-site data analysis system has been installed, programed and de-bugged, and a minimum of 4 I
operators, fully comprehending the operations required to process and edit data entered into i
l the system will be available for this test.
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PERF Page 10 Rev. 2 - 5/16/78 l
- 12 THP 4030 STP.202 3.4 Verify that the following initial conditions have been satisfied imediately prior to pressurizing the containment.
3.4.1 The emergency back-up batteries for containment lighting have been disabled.
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PERF 3.4.2 The door between the instrument room and the lower containment is open.
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PERF 3.4.3 The containment has been cleared of all personnel and the personnel air locks have been locked closed. f 3.4.4 AllcontainmentlightshavebeenexNNguished.
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4.0 PRECAUTIONS PERF
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4.1 Scheduling of this test should be made, insofar as feasible, in accordance with advance weather predictions to avoid large or abrupt changes in atmoshperic temperature or pressure.
4.2 Radiation Protection shall be contacted prior to the supplemental test and depressurization so that radiological conditions inside the containment can be verified safe for the release of containment air to the outside environs.
4.3 The area where data collection takes place should free of radioactive contamination so that unrastricted access to test equipment and data collection stations is possible.
4.4 The Ice Condenser average ice bed temperatures should not exceed 24*F.
4.5 Do not exceed the rated capacity of the Pressurization Test Air Dryer as this could result in the admitcance of unacceptably high humidity in the containment.
4.6 The containment ventilation system shall be used if necessary to maintain lower containment average temperature below 100*F and hot spot temperatures below 120*F.
5.0 PROCEDURE 5.1 Pressurization 5.1.1 Place the containment pressure test air dryer in service as per operating procedure 1-OHP 4021.064.005 (record time in the test log as comencement of the pressurization period).
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1 5.1.2 Monitor the following data on an hourly basis:
Containment Temperatures Containment Pressures Containment Dew Point Tenperatures Page 11 Rev. 2 - 5/16/78
- 12 THP 4030 STP.202 Atmospheric Temperature Atmospheric Pressure The Exact Time Use 'ILRTEST' to process and summarize the data.
ILRTEST is progransned to correct ' raw' pressure readings only in a narrow band around Pa. The small error in corrected readings resulting from being below this band is acceptable for the purpose of monitoring pressurization.
5.1.3 When the containment has reached tne test value 12.4(+0.1,-0) psig, remove the Containment Pressurization Test Air Dryer from service as per Operating Procedure OHP 4021.064.005.
NOTE:
Pa=12.0(+0.5,-0.0psig). To ensure that Pa is maintained throughout the test period, the initial test pressure is specified 12.4 (+0.1, -0.0) psig.
5.1.4 Close the isolation valve on the test pressurization penetration.
/
OFER 5.1.5 Verify that the time the Containment Pressurization Test Air Dryer is removed from service is recorded in the test log.
Identify all data collected up to this point in time as pressurization period cata.
/
PERF 5.1.6 This mark:: the beginning of the stabilization period.
Record time in the test log as " Pressurization Period Ends, Start Stabilization Period".
/
l 5.1.7 Verify the test pressurization spcol piece has been removed and the test isolation valve blanked off.
(
/
MAINT 5.1.8 Verify the leak-tight integrity of the blanking flange by a " bubble test" or using the Volumetrics Leak Rate Monitor".
/
PERF 5.2 Stabilization Period l
5.2.1 Monitor the following data every half hour:
Containment Temperatures Containment Pressures Containment Dew Point Temperatures Atmospheric Temperature Atmosphoric Pressure The Exact Time
/
Use 'ILRTEST' to process and sumarize the data.
ILRTEST may also be used to obtain a preliminary leak rate indication.
Page 12 Rev. 2 - 5/16/78 l
,,rg
,p.,,,
m-,.
m g.
-p,,-,.v
-y 7g-m,,
e
,-,-y,
..--w-,3y
-a... >-,,,.
y
r" m12 THP 4030 STP.202 5.2.2 Meeting Stabilization Criteria:
5.2.2a The duration of the stabilization period has exceeded the minimum of four (4) hours.
/
5.2.2b The containment has been maintained at a pressure of 12.0(+0.5,-0.0) psig for a minimum of two (2) hours.
/
5.2.2c The weighted average temperature in the I
Upper, Lower and Ice Condenser compartments l
has not varied more than 0.1*F/hr over the l
last four (4) hour period.
/
l 5.2.2d No single Upper, Lower, and Ice Condenser Containment temperature reading has changed j
more than 0.5'F during the last hour of that stabilization period.
/
5.2.2e Due to the cyclic defrost operation of the Ice Condenser AHU's and the higher than nonnal heat load in the Ice Condenser while j
under pressure, temperature criteria 5.2.2 c and 5.2.2 d as they apply to the Ice Condenser may not be met.
In this case, and only after all other stability criteria have been met, 5.2.2 e and 5.2.2 d as they apply to the Ice Condenser may be waived. A record of level of stability that was achieved in the Ice Condenser shall be made in the test log.
NOTE:
If Stabilization Criteria cannot be achieved or indications of the leak rate are unfavorable, j
at the discretion of the test engineer and with the concurrance of the Technical Department Superintendent, the test may be aborted and a search for the leakage source (s) begun.
5.3 Integrated Leak Rate Test If stabilization critiera have been met the ILRT may begin.
Record the time in the test log as " Stabilization Ends, Start ILRT".
/
NOTE: The starting time of the ILRT may be moved to a later point in time as in some cases this aids the convergence of test data to a solution in the l
linear regression program. Restarts should be identified in the test log as " Restart No.
l Computer Run No.
l Page 13 l
Rev. 2 - 5/16/78 i
=
- 12 THP 4030 STP.202 5.3.1 Monitor data in half hour intervals as in the stabilization period. Use ILRTEST for data processing.
5.3.2 Meeting ILRT criteria 5.3.2a The duration of the ILRT has exceeded the mininum of 12 hrs. and the clifference between the 95%
upper confidence leakage limit and the leakage rate itself does not exceed 0.0625 wt %/ day in the 3
most recent data set. After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the 0.0625 wt
%/ day criterion may be waived if it has not yet been met.
I i
r 5.3.2b The leak-rate, as detennined by the linear regression 95% Upper confidence limit has converged to an acceptable level.
f Lam /95% < (0.75 La
" Type C Leakage Penalty) 5.3.2c The Upper confidence level leakage and the measured leakage do not show a negative trend over 3
the last four data runs.
f 5.4 Supplemental Test If the ILRT criteria have been met, the Supplemental Test may begin. Record the time in the test log as "ILRT Ends, Start Suppitmental Test".
/
NOTE: The starting time of the S>pple. mental Test may be moved
(
to a later point in time as in some cases this aids i
the convergence of test data to a solution in the linear regression program. Restarts should be identified in the test log as Supplemental Test Restart No.
Computer Run No.
NOTE: Radiation Protection shall be notified of the next step.
5.4.1 Establish a 3.0 scfm (-0.3, + 0.2) leak by valving in the test flowmeter.
(Use temperature and pressure correction data along with flowneter calibration data to correct the flow rate to standard conditions.)
See Appendix 0.4.
/
3 5.4.2 Allow a minimum of 30 minutes for the imposed leak to stabilize before taking data in the supplemental test period, and th6n take and process data in half hour intervals as before. In addition, monitor flow rate and pressure.
/
5.4.3 Meeting Supplemental Test Criteria.
5.4.3a The duration of the ILRT has exceeded the minimumofsix(6) hours.
/
t
{
5.4.3b The sum of the imposed leak and the leakage measured during the ILRT is within + 0.25 La of the composite lea'kage measured iii the s
supplemental test.
/
(Lo + Lam - 0.25 La) < Lc < (lo + Lam + 0.25 La)
Page 14 4/2/40
.Rav. 3
,_-.e..
-._.,__.._.,,m
, - _,__..m_..,
,y,,,,,--ve, m
-,.m4.mm.,
y
._._m.e,m,w,,r__.w-.,,...ww,,,w- -. - - _ - - -,
,---,,-.ws,.-
- 12 THP 4030 STP.202 l
5.5 Post-Test Depressurization 5.5.1 Radiation Prote on shall perfom manual air particulate / radio gas samples of the containment air to ensure that it is safe to ralease to the outside environs.
/
5.5.2 Bleed air off through the pressurization penetration (CPN-57) as dictated by R/P survey results. (It will be necessary to remove the blank flange from the end of the pressurization spool piece).
f 5.5.3 Restore containment lighting, perform an inspection of the containment, end restore control air to the containment. (See Apr.B.4 for details.)
/
5.6 System Restoration 5.6.1 Remove pressurization test line and restore both blank 3
flanges at CPN-57.
/
MAINT 5.6.2 Replace equalizing hatch in the operating deck.
MAINT 5.6.3 Restore containment vent fan containment isolation 4A and $B and NESW low flow interlocks to nomal.
C&I 5.6.4 Restore instrumentation and control devices vent per the instrument list, Appendix Bl.
/
C&I 5.6.5 Restore the containment pressure safeguards instrumentation to nomal.
4 PPP-300 PPP-301 PPP-302 PPP-303
/
C&I 5.6.6 Restore the Loop 3 standpipe to nomal and remove the television monitoring system.
/
C&I 5.6.7 Restore the ice condenser drains to normal by isolating WD-302 (WD-301 Unit 2), removing any temporary 3
equipment and opening the normal drain isolation valves.
/
5.6.8 Restore the ice condenser and glycol systems to MAINT normal:
5.6.8.1 Restore the glycol supply system line-up to noma 1.
/
OPER 5.6.8.2 Unblock SV-123 on Unit 1 or SV-124, and -137 on Unit 2.
/
I OPER l
Page 15 l
Rev. 3 4/2/80 l
I
- 12 THP 4030 STP.202 5.6.8.3 Remove safety valves temporarily installed at R-150 and R-152.
/
4 C&I 5.6.8.4 Replace pipe plugs on the ice condenser equipment access doors.
/
MAINT 5.6.8.5 Unblock VCR-11 and VCR-21.
/
C&I 5.6.8'.6 Restore leads lifted from AHU d/p switches and infom Operations that defrost is back in auto operation.
/
C&I 5.6.8.7 Unblock lower ice condenser doors.,
3 1
l
/
PERF 5.6.9 The test connections on MPP-210. -220. -230, I
and -240 have been isolated.
/
C&I 5.6.10 The " Valve Alignment List" found in Appendix 8.5 has been given to the SOE so that the alignment may be placed in the desired status.
PERF 5.6.11 The spare dew point hygrometers have been removed from the containment and the nomal hygrometers have been restored to normal service.
i C&I 5.6.12 Sample lines for the lower containment dew point
[.
nygrometers have been reconnected to the Lower Containment Ventilation ducts.
/
C&I
(
5.6.13 The Containment Air Temperature Test RTD's have been removed from the containment, and their associated bridge cards and power supplies from the LRT test panel and returned to Perfomance for storage.
/
C&I 5.6.14 The Mensor Manometers have been returned to Performance for storage.
/
C&I 5.6.15 The test connections on PPA-310 and -312. PPP-302,
-303, and PPX-301 have been isolated.
/
C&I 5.6.16 The 0-30 psig Heise gauge and Brooks flowmeter used in the supplemental test have been returned to Performance.
/
C&I 5.6.17 All other miscellaneous equipment used for this test has been removed.
/
PERF 5.6.18 The load cell readouts for the polar I
cranes have been re-installed in the containment.
3
/
C&I l
Page 16 Rev. 3 4/2/80 l
- 12 THP 4030 STP.202 5.6.19 All bottled gas that was removed from the containment in Step 3.1.10 is returned.
j
/
.r_
MAINT 5.6.20 The following sections of piping are to be refilled with water (see sketches Appendix 8.2) 5.6.20a The primary water line between the hose connections used for reactor cavity scrubdown and DW-207 for Unit 1 or DW-208 for Unit 2 (Ref. Dwg. 1-2-5115A).
/
OPER 5.6.20b The primary water line to the PRT between PW-272 and PW-276 (Pef. Dwg.
1-2-5715A).
/
OPER 5.6.20c The :entainment vent unit drain lines (Ref. Dwg. 12-5137A).
/
OPER 5.6.20d The ice condenser fan cooler unit drain line 5 (Ref. Dwg. 12-5137A).
/
OPER
(
5.6.21 The vents on the following systems or portions of 3
systems that were opened in Step 3.1.2 are to be closed. (See sketches, Appendix B.3),
5.6.21a Vent line from PRT relief tank.
/
l OPER 5.6.21b Reactor Coolant Drain Tank
/
OPER 5.6.21c Reactor Coolant System
/
OPER 1
5.6.21d Accumulator Tanks
/
OPER j
6.0 ACCEPTANCE CRITERIA The results of this test shall be acceptable when the following l
specifications have been verified.
Page 17 Rev. 3 4/2/80
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at Pa.12 psig, during each 10-year service period. The third test of each set shall be ex ducted during the shutdown for the 10-year plant inservice inspection.
b.
If any periodic Type A test fails to meet.75 La, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.75 La,'a Type A test shall be performed at least every 18 months until two crTsecutive Type A tests meet.75 La, at which time the aDove test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy cf the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La.
2.
Has a duration sufficient to establish' accurately the change in leakage rate between the Type A test
(
and the supplemental test.
3.
Requires the quantity of gas injected into the I
containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at Pa, 12.0 psig.
f.
All test leakage rates shall be calculated using observed data converted to absolute values. Error analysis shall be performed to select a balanced integrated leakage measurement system.
Test Performed By Date Test Reviewed By Date Approved By Date l
Test Signed Off In Master STP Log Date Page 18 Rev. 2 - 5/16/78
.o
- 12 THP 4030 STP.202 INDEX OF APPENDICES A.
Code of Federal Regulations 10CFR50 Appendix J Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
B.
Preparing the Containment for the ILRT.
B.1 Instrument Venting List B.2 System Draining Sketches B.3 System Venting Sketches B.4 Pressurized Gas Systems Venting Sketches B.5 Valve Alignment List.
C.
Preparing Test Equipment for the ILRT C.1 ILRT Pressure Instrumentation Installation Sketches.
C.2 Supplemental Test Instrumentation Installa-tion Sketches.
D.
Preparing Documents and Data Analysis Programs for the ILRT D.1 Type C leakage penalty form.
D.2 Instrument Calibration and Certification Summary Form.
D.3 Fixed Information Data Coding D.3.1 Data Card A1: RTD Conversion Constants and Run Control Indices.
D.3.2 Data Cards B1-B3: Hygrometer Calibra-tion Constants.
D.3.3 Data Cards Cl-C7: Manometer Calibra-tion Data.
D.3.4 Data Cards 01-05: RTD Weighting Factors.
D.3.5 Data Card El: Volume Weighting Factors.
D.3.6 Fixed Information Data Coding Form.
D.4 Supplemental Test Flcw Standardization
{3 E.
Data Sheets E.1 ILRT Data Coding Form E.2 Pressurization Data E.3 Stabilization Data E.4 ILRT Data E.5 Supplemental Test Data Page 1 of I f2I8b
APPENDIX A N 2 THP 4030 STP.202 PART 50 o LICENSING OF PRODUCTION AND UTILIZATION FACILITIES e.sivated at the iomuone here tae food amwees i pathws's astually entst: aan s.
conisi-nt iseiacea vain muns 2*. The calculated martual total quant!!y a
on CmatWM MaH M.
any vaave wnten as reised upon to penorm a of tod:pe=331 la gaseous eSuents should not a rom wa;sa. coot.aa mwn asacroma Contain: Dent laolattos Junstloa.
eseeed 1 curie for each tirat-water.cooted I. Introdueuen.
C.
- Reactor containment leakage test pre.
t,uclear pomer reactor at a site.
II. Espinastnea of terma.
gram tactuo the performance of Type a.
- 2. Notwithstand:ng the guidance ta para.
III. Imakage test requirements.
Type 3. and Type C tests, demenbed La III.
21.0, and ItJf. respectivety.
grapha C.1 and C.2 for a p&rtlCular site. If an A. Type A test.
D. "I.eakage me" tw test purposee le 464 applicant for a permit to construct a tight-
- 3. Type 3 test.
water. cooled nuclear power reacter has pro.
C. Dpe C test, leakap watca ocm in a unit W ume. stated as a percentage et weignt of the ortstnal con.
posed hotellSe In=plaat control measures 8 to D. Periodle retest achedule.
tent of containment a:r at the letrage rate reduce the poeatble ' sources of rednoactive IV. SpWlal test requirementa, test pressure that escapes to the outside todar.e rolessee. and the calchleted easual A. Contanament snod1Scauons.
atmosphere durteg a 24-hour Wat period.
quaanttee tMang into assoual euch usetrol
- 3. Multiple leakage-barrier containrsents.
E. "Outrall integrated teskage rate" meara V. In8pectnea and repert:ng of tests.
that leakage rate whica obtains from a num.
mratures escie4 the design objective quan.
A. Containment taspectnea, mation of leakade intSugh all poteattal leak.
1:t:es  forta la paragraphs C.1 and C.2 B. Deport of test resulte.
age patna incluaang contatnment welds.
the requirements for design object!ves for radioactate 13 dine and radioact3ve gr'.tenal
- 1. IsrTaceWtWest valves. Attings. and components which pene.
trate conmament.
14 ptruculate form la gaaecue ofRuests stay Coe of tae sendittend of a!! operating P. "T}ye A Tests" mearts tests intended Ic be deemed to have been mit provided tne ca:culated annual total quantity of all ra.
licemass for water. cooled power reactors as maaun the pnmary nac*.or containment d'cactare lodine and radioactive material ta spec 1Aed la 5 4044(o) is that primary re.
onin11 Integrated truage rate (1) afW the j
par *te:Inte form that 2nsy be rolessed la actor contataments shall sneet tce contain.
can'.alament haa mn completed and la nady ment leakage teos requireemente act forth tw operation, and W st pe sodat intenaJs gaseous ecuents does not escoed four times La th!a appendia. These test requirements IA". "* Type 3 Testa means tests totended to the quacuty calculated pursuant to para.
p3, tee for preoperatteams and persodie vert.
O graph C.1.
i Aantaea Dy teste of the sema.ttant lategrtty detect local leaks and to measm leakage 140 yR 19442. May 5.1975. as amended at 40 of y1t 4C018. Sept. 4.1975. 40 FR 88047. Dec.17
',7,
,t 11mattrig boundary for the following primary s
acreas each pressure-containing or leakage.
1 n.
1973. 41 yR 19447. Apr.19.1978) g g,g,,g,g
,,g,,,,,,i,g p,,,,,,,,g,,,
pactor containament penetrattens:
and estat11st the acceptanos criterta for
- 1. Contaannunt pmtratsens wheee desf rn such tests. The purposes or the testa are to incorporates restilent seals. gasmeta. or se=2 ant nasure that (a) seenage through the pet.
- P** P P'".8 P***tions e rted with u.
Inary reactor contatament and systems and panamn bellows and electncal pmtrationa cotr.Anente penetrating primary contain.
Ment Shall not exceed al1oTable leakage rate 3tted ylth f e11ble metal seal assemblies.
Talues to speci$ed in the technical spec 1*
- 2. Air lock door assis. inc!Uding door operat.
Acations or aseeclated bases and (b) per$odig Ing mechanisnt penetrations watch are part survedlance of reactor containment pene*
of the containatnt pTeasure boundary.
trations and teclation veJ9ee la performed
- 2. Doers with resutent semis or gassets es.
so that proper snatstenance and repairs are capt for seaseweided doors.
)
made during the service !!fe of ths contain*
- 4. components othat than those Itsted is
[
mertt. and systems and componenta pene.
22.Q.1. ILQJ. or II.QJ whsch must meet the 1
acceptance ertterta ta fILBJ.
trattag primary coctainanent. These test requirements may also be used for guidance ag,."TTpe C Testa" means tests intended to in estab!!anter appropriate containment measure containment isolation valve leakage C*
laskage test requirements la technical epec1*
rates. The containment isolation valves in. ~
Acations or associated basse for other types tiudod are those that:
I of nuclear power reactore.
- 1. Provide a direct connection between the Inside and outside atmospheres cf the pri.
II. Earmvtose orTEstas snary reactor containment under normal op.
erstion. such as purge and ventilatloc.
A. "Prtsaary reactor con".atninent" monna the structure or vessel that enciones the com.
vacuum re11ef and tnatrument valves:
1
- 2. Are requ: rad to close automa&Ically upon ponents of the reactor coolant pressure rece pt of a contatnment isolatten signat In j
boundary, as deSned in 5 50.2(v). and serves sa an saaentially leak.ttght barT:er agotast the response to controla intended to efect ocu..
tainment isolation:
uncontrolled release of redlemstivity to the
- .4 envircasr'est,
- 3. Are requtred to operate intermittently g under poetaccident "v: and l
- 4. Are in main steam and feedwater pigtag I and other systems wt:1c= penetrate ccataan.
ment of direct. cycle boiling water power reactors.
Z. Fa (p2.1.g.1 means the calculated peat containment internal pressure related to the j
design baals accident and spect$ed'etther in the techntent spec 2Aestion or associated bases.
J. PS (pJigd means the containment f
vesset reduced test pressure selected to mean.
ure the Integrated leakage rate during pe.
Flodic T)pe A tests.
K.I.a (percent /24 hours) means the mast.
mum allowatle leakage rate at pressure Pa as spectned for precperational tests in the technical spec:Scations or asacc!sted bases, and as spec: Sed for periodic testa in the op.
ersting license.
- 1. IA (percent /24 hours) means the de.
sign leakage rate at pressure. Pa. as spectaed in the technical spec 1Scations or ****ted bases.
(
ht. Lt spe* cent /24 hourel means the maal.
I mum allowable leakage rate as pressure Pt derived frorn the preoperational test data
(
- Such in. plant control measures may in.
as spec 1844 in !!LA.4.(s h t11).
I cluce treatment of steam generator blow.
M. Lam. Ltm (percent /24 hcurs) means
(
dow. tank exhaust, clean steam supplies for the total measured contatnment teskage totes
(
turnine gland seals. condenser vacuum sys.
at pressure Pa and Pt. respectively, obtatned
- ms, containment purging ennaust and from testing the containment with rompo.
- t!!stion exhaust systems and soectal de.
nents and systems in the state as close as I
. n features to reduce c=ntaminated steam practical to that whten would exist under
.no 1; quid leakage from valves and other design bssis accadent conditaons te g terited, sources such as sumps and tanks as sp.
dratned. Sooded or pressutued).
proprtate for the type of reactor.
O. " Acceptance criteria ' rneans the stand.
are eastnat which test resu!Ls are to be Page 1 of 3 Rev. 2 - 5/16/.18...
l APPENDIX A
~
- 12 THP 4030 STP.202 PART 50 o 1.lCENSING OF PRODUCTION AND UTIUZATION FACILITIES see,g,edfe, a unisgta.fonetanai =.
contaame.t intataa es~e := ne arsiema m If two co e,8.buisy a tne e stainmaatan a teenage etesed ta nra.t.edi enau be tesad in u.
teste faa io me n=euues putodie type A ta. a,pitc.mie ease,.ane.
nmtungouuda.7 cordas e esa tu.c. ne mes wed wasat.
er tena = zu.tscos, not-thai dtne the i
.rzz.t.wtass7sria ma= = =orm rue imm tas toi. ahain b. r ported i. ts.
pertadio retest acaedui. o.f zzto. a Tf,e A c o-.a.
tot s3ait be,e,fo,med a enco,iant a..t.
Tram c9nstating of a schedule fee con.
- 2. Coeldust of tests. Prosperational tenhage down for refueling or approstrnateep every b*
Type.t. 3. and C testa anan be Co.
rate testa at either reduced or at pena pres.
IS anontha, whicaever occura Arzt. unt4*. two for lea's teattng the primary tvector sure. asaa be conducted at the latarva&a consecuttee Type A testa meet the steep ante
)
a
. ament and related' systems and carape.
epectaed la D.
ertteria La 13.A.s{bp. af ter which tiesi the a:esta penetrattag primary cessa. ament pres.
- 3. Test methods. (a) ALI Type A testa ahaa retest schedule spectaed an 11tIL seay be sure boundary.
be coeducto 3 la accordance wtut tne provt.
resumed.
Upon completion of constructies of the alons of the Americas National standard
- 3. Type 3 rests.
primary reestar contetament, tuatustas ta.
N63.+.1ST2 Lead. age saae Tesung of coa.
- 1. Test methods. Acceptabte meene of per.
stattet:sa of all portsene of metassacal. 3aste, taasaneet Strussures far Nustear Monsters, formist e preoperStesent and persedae Trpe electr+ cal, and instrumentataea systema pene.
Maech 361973.5 The method c3 casa for the-3 testa laciudet.
traung the petmary reester aseta4aansas lasism4-ame ahaa merma&&y be used for taa (a) Zaamlastlos by ballde leakgletettlest pe,ssure boundary, and priorto esp reestor P=8tedae testa, method (or by otaer equivenent test methans (perstang period. preopersuonat mana portadae
. (b> The assurney of any Type A taes ahall auch as maae spectrometer) of a test chtan.
Itosye rate testa, as applientie. sAael be, be vertaad by a supplecleasa& tess. An acceps.
ber, pressurt2ed with air, nitrogen, or pnees.
conduc*ed an accorsance mata thefat:ewings maae asuned la danartbed in Appendia C of matic Sute spec:2nd la the technicat A. Ty.ee A test-1. Prefett reguaremente.
ANSE 26ed.4.LFf3. The euppaennestaa teos spectacations or==.aetated bases med most.
(at Containments inapactice la---
W tatossad she&4 be conducted for sung.
atructed as part of ladieseust oestatement with v.A. sas;t ne performed na a peerwtuantsen stems durssima to usabilaa soeurata;y sne penetrat'ana, to the parformance of Type A tassa. Duttas canade la teamade rase betwna the Ope A (b) Measurermans of the rete or pressure the perted between t%e initiatles of the ces, ame naspyteamentaa tea. 3mousta from this,
ions of the test chambee et tae e,etusment.
l tainment inspecuen and tae performance of suppleaneataa teos an, acceptable proeided.
penetration pressurtzed wita air. mtrogen.
the Type A test, no repatro or adluatmeate the dagennes between the supplementaa taas or pneutnatic suid spectaed in the techonnent anait be made so that tae containment cas data a 4 tae Type A taas data la witssa 0:3 spectacations or associated baase.
1.4 (or oss Lt).If reunta are not witsin oas be tested in. as c:sse to the,"as.a.c.coaditten (c) Iankag g 0 = g.,=,,g;mo,,a,eb= y,de =
,e,ma.enu,,e s.uremtance by means of a m,,s.uc, m,m to.
ia..een the n..aued s,ste,n w,ut,,0 ia.ons comptetton of one Type A tons and the tattia=
tJos of the conta13 ment taapectnam for the cessful supplemental set MM
! F conttnuous or in ermittent pressortsation of individual or groups of containment pene.
Subsequent *!be A test, repaire or adjust.
(c) Tut leakage rates sh 1 e calculated trations and measurement of rate of pres.
ments shalt be made to components whose using aDaeh.&e salues corncted for instru*
eure loss of air. nitrogen, or pneumatst itute f
teokste esteeds that specided trrtae tachstcal tnans error.
opectaed in the technical spect2:stion or t
spectScation as scac,n as practical af ter iden.
- 4. Preopamtione! leakere rete tests. (a) anacciated bases through the leak paths.
tl8 cation. If during a Type A test. Including Test reswe-(t) Aedated pressure fests.
- 2. Test Pressure. A11 precperational and the suppNrental test specalled in !!! A.3.(b).
(t) An $ntt;al taet shall be performed at a pertodio TypJ B tests shalt be performed by potentta:ly escessive leakage paths are Iden.
preneure Pt. not toen than 0.30 Pa to measure local pneumatic pressurization of the con.
tified wh!ch us.1 Interfere with sattaltetory a leakage rate Ltm.
tainment penetrattens. etther individuatty or completton of the test.or which result to the (11) A escend test shall be performed at la groups, at a prewte not less than Fa.
Type A test not meetlog the acceptance crs.
pressure Pm to measura a leakt.ge rate Lam.
- 3. Acceptante criterts (See a'so Type C ter a I!! AA.(b) er!!!.A 5 tb).the Type A test (til) "I*ae leskate characteristics y!elded tests.) (a) The combined leakage rate of att shalt be terruinated and the leakage tarough by measurements Ltm asid Lam shall estab.
penetrations and valves subject to Type B
'aths shall be measured using local Itth the nazimum W10webte test leakage and C tests shall be taas thea 0 60 La. with
/*
,(
testing trethods. Repstre and/or rate Lt af not amore thart La (Ltrn/ Lam). In the exception of the valves spectiet in (.
tents to equipment shall be made and the event L(m/Zam la gTeater than 0.7. Lt III.C 3.
A test performed. The enrrective ac.
shall be spectaed as equal to La (Pt/Pa)h8 (b) Isakage msasuremertta obtstned b
akert and the charige In leakage rate (2) Preis presare fests. A test shall be per.
through component leakage survell!ance sys.
getermired fross the testa and overail inte.
forme 4 at pressure Pa to measure the leakage tems (e.g, continuous pressurtsstion of an.
grated leotage determined from the local test rate Lam.
dividual containment components) that and Type A tests than be included la the (b) Acespiance erfterie-.(1) Jtaduced malatatna a prewure not lean than Pa at in.
pport submitted to the Commiss6ca as spe*
pressure tests. The leakage rate Ltm shall be diridual test chambers of containment pene. t f
tifted in V.B.
less than 0.13 Lt.
trations during normal reactor operatson.
1 (b) Closure of contatament isolatloa valves (2) Pesh pressure fests. The leakage rate are acceptable att lieu of 'IWe B testa.
M*
for the 'I'/pe A test shall be accoespltahed by
!.am shall be less thaa 0.73 La and not greatee C. Type
- C teste.
I norman operation and withous any preilml*
than Ld.
- 1. Test method.TFpe C testa sha!! be per.
}
stary esercistag or adjustments (e g. no 3, pernodia feeksee refs ferts.-(e) yest pre,.,
fom.e4 by local pressurtzatters. De pressure l
tightenant of valve after closure by valve sure. (1) 7teduced pressure testa sha11 be sha11 be app!!ed la the same direcuan ma motor). Repaus of Intloperating or leaking conducted st Pt.;
that when the value would be required to i
valves sha:1 be made as negensary. Informa*
(2) Pea's pressure tests shall be conducted perform its safety function. unless it can I
tion on any valve closure malfunction or l
at Pa.
De determined that the reeutta from the tests entre leakage that requires corrective metloa (b) Accrptance criterie==(1) Rednerd a for a pressure apptled in a dlSerent direcuen l
before the test, shall be included in the re=
pressure rests. The leakage rate 1.tsa shall be wu! provfde equttalent or more conservattre port submitted to the C---~ ~ - n as spect.
gene thma 0.75 Lt. It local leakage measur,.
teoutta. The test methods in !!!Al may be IkedLa V.B.
ments are tehen to efect repaars la order to substituted where appropriate. Each valve to I
(c) Tas conta;r. ment test conditions shall sneet the acceptance criteria. these measur,.
De tested shall be caused by nortral opera.
Etabittse for a pr tod of about 4 bevis prior mente sball tw takaa at a test pressure Pt.
tson and without any prettmanary eseretstag 19 the start of a les1tage rate test.
C) Peet preneure teers. The leakage ante
- ce adjustments te t no tightening of vatte 1
(d) Those portions of the fluid systema Z am aha:3 be leas thaa 0.73 La. 2f local leak.
aftee closure by valve motor).
.I 1'
that are part of the resctor coolant pressura age measuretz:ents are taken to efect repatrs 2.. Test pressure. (a) Valves, unless pers.
boundary and are open directly to the con.
In order to meet the acceptance criteria, surtred with flutd (e.g. grater, f.ttrogen) tinament atmosphere under post. ace 3 dent these measurements shat! be taken at a test, front a seat systern, shall to presourtzed with condittons and become an estenstort of the pressurf Pa.
air or nitrogen at a pressure of Pa.
boundary of the containment shatt bo opened
- 6. Additional Jtequirements. (a) If any ab) Valves which are seated with flutd er vented to the containment strnosphere periodic Type A test imus to meet the app 14 from a seat system shalt be presse.ted wtt3 prior to and during the test. Porttons of cab!s acceyance criterts in IIIh(b). the that fluid to a pressure not less than 1.10 Pa.
ale.ted systeers inaMe containment that pene.
test schedu:e applicable to subsequent Type
- 2. Acceptance criterios. The ambined trat? containment and rupture as a resu:t of A testa will be teetewed and approved by the Inka: e rate for all penetrations sna valves a loss of etolant ace! dent stiall be vented to Comm!.as803.
the co itain=9ent atmmphere. Att vented sys.
Sub;eet to Type B and C tests shall be less than 0 60 La. Lestage from containment tera.3 shall te dealfted of satet er otter httda to the ettens necetaary to assure esposure of
. ANSI N45 4-1972 Isakage Rate Testing of bilation valves that are tested with Guid the system containment taolation va2res to g 3ntainment Structures for Nuclear Reactora frent a seat s) stem may be esetuded shen er-*Hnra.ertt Mr test pressure and to assure (4ated liar. Id.1972). Copfes may be ob*
otternuntng the combined leakage rate:
Prorrf nf.That-112 be subjected to the postaccadtnt ha roh.~the Arnericant Nuetear Society
- Suc% va$vas bare been demot.strated
.(
sm)
.t'a3 prehure. Systems that are re.
n ue, date. IL 60524.
. f. '
A p ts avaltab!e for Inspection at the g, g,3 e.tutd leaka e rates that do not es.
to teaantrtn the plant in a safe con.
Curtrg the test shaJ1 be operatHe trt C
t n s P bN Document Room.1717 rted thase spec #.e4 in the technical spect.
nor:nal mode. and need not be vented.
N Street NW, Washington. DC. The ircee.
ikaue'n er assc*tMed bases
- and Syster=.s that are nyrnasty Sited with mater. mt no. by refer nee was apr'ored by the
[
[
I tend operating us. der post.acetdent c'3ndt.
gi.ter un Octo-tions. such as the containment hest ternoval
,.sure tue seat!93 funetton for at least 33 cratem. n ed not n. v.ni.d. wo.eser, th.
davs as a pressure et 1.10 Pa.
3,,,a,, 3 3 7,,,,,,
50 36 Page 2 of 3 Rev. 2 - 5/16/78
APPENDIX A
- 12 THP 4030 STP.202 PART 50 o LICENSING OF PRODUCTION AND UTILIZATION 1:ACILITIES D. Perseder reerst seasdele-l. Tree A
- 3. Jtezeer of test reentes.1. The proepers.
Ap=eween E-ECCS Evassavesse Meems tre'., t al Af ter the preeperattanal lessage tional and period 1C tests analt be the euBject
{ Required aad Ace 5Lable Features tf
, raa tests. a set of thru Type A teste shut ne of a sununary technicas report summitted te zrsusuon undes part.stmed. at approssmately equal Intervais t3e gy,gger af Muglear Bene 9er II. %And meumenstaca.
dertne, eaen to. year set eseo period.1?ie third et i g gg ym W f
.t c:=gg mte set m een.uo.4 m. nth.
(
,, ant 1. sm te,-,m, m ip.yes,,iot m.
= =. m e = =.,, _,,,
- .see _..e
,m.aeta - e.o or e
,,a - e.
..e-r servire,insp.etwne,e afm me e-ua of es.taately 3 appres meathe e,m.,m.
erie
,.c t.aung. The
- t The -
^3~~
raa'<-~= ~ ~
shM1 De $100 t te 1 ted in as to perfJrmance of Typ in imernt.4 "Reester Centalrment Sullg.
te,m,e.tm een t,e A tesla s. hall b,e timited uon= =am To-n.m> au e, ant fa m s.is nea.
mt e,,,a,a, oo,,_ou,, e, a,o.,
,e e, se,a,e.e, m omes,,e,,,en e me, e
u.e4 uteown
. T,e re,.,t en ti,e,,sepeauenti iest fondit:St GrCtr the admir.1strative control sh4 !actude a schematne arrangement of the leve
,,,,l its allow for such u, seer.alause_as in-a~ Bn a deared. man,e m. o,e.4,et,-edu,es
.ame m. Reas.u,. ment.fstem. the m.
,e,,,,a,a,s,oo,n, e.,0,,,..e m,, one m,s.A,m
,e a
. th e i,,e..
m.amoon u. o e.uppi.memi tm
,c e ewed o,e f.,2. Type 3 terts. Type 3,orm.t.s.see,ept testa nae.thod. and the test preefam se6ected sa ap*
tes a,sestaeatione.,A range o,f power,di,s,trieutson, a
air im nan.e pe, so a.ie to ope,m.au m t. - ma
,emor..,me-fe, refu.
.g..u,ag on.t,
,i
,o.e, d,and,,umoama,ns,mt ma,, eesu a,e, e
as. ors e
,enient miem but om.e ca.e at inte
.ont. duett,r,ted.e - n. rep-ahau 0u- -
.e at, see, m m.a ama.ta an. --prmmen - m es,e memme ab etud ed and the e.,
grotter than 2 yesra. Air teens sha41 he tested teskate rate test data for the Type A tent asleeted Should De that which resulta La LM at gam 02th interval 8.
Steetter. sit letta requite 94 the estest necessary to deanen*
Most severe calculated consequeness. for 1244 which are opered durtag such intervals, shall strate the meseptat111ty of the contatament'8 spoetruss of postulated breaka J.R.!! alagte be tMted E!:t, eaCa opening. For primsFF -
leaitaec role la meelLDS the acceptahee fagures analyend, reatter caciat<tment penetrataeas emplertag' ertteria.
- 1. The Knetrat 3tered beerpy in tJte Fuel.
a feStianova lesdage menstering orateln.
- 3. F3r enth periet )C test. leakage test re.
The steady. elate tempefature distributloh 8
Type 3 te.ta, esteps for tents of att locks.
g.ilta from Type A. 3. sad C testa shall be re.
and etered eserfy tr. the fuel before the hy.
rmay, natwituttanding the test schedule spee.
por*ed. The report shall contain an analyses pothatleal accident shall be calculated fue 1844 ur.dPr !!!I 1. De performed every ott ?
and Interpretattom of the Type A test results tae bwa.up that ytends the hagaest emieu.
reactor shutdes a for fofusting but in ne case and a sumamary analyste of perledic Type 3 lated sladalag temperattare for, optionally.
at b'.ef-*Ma greate? than 3 years.
- 3. Type C sests. Two C testa shall be per.
tad Type C tests that were performed sauce the. highest calculated stesed enemy.) To formed duttr.g etert reactor shutdown far re.
N last Type A '.est. lashage test Moults assemouah this, the therenal conducuttty of the CO, shall to evaluated na a funetloa of fuettne but in ne came at interrats geester from Type A. 3. and C testa that faced to bure.up ma.d temperature, taking inta con-than 3 years.
Dneet the acceptaaes crlterta of !!!A3(b).
sidersuon d12erenese la 1alttal deastty. and ZZZ.3 3. and IILC1 resportively, shall be re.
the theriant conductanes of the gap beteena IV. Spectaa Tsartwe Reetrtacatzpfe ported la a apparate secosepanytag summary the UO, and the cladding asalt be evaluated I
A. Centstantent medulcotten. Any major report that includes an analysla and inter.
as a functies of the burn.up, taktag into WhB8RM8M N W N*B
- metScatt c
.h.c,h.en. en, replacement of a,e.o.mponent pretattan of tDe test d.ata, the least. squares 8=. g,,,,,, q=,,y",e g,;g 1,m of m pm na,,
or een.
At meaim,,s a m.e test.
th. instmmem.
a
- tai, t boundary..,,eeesiing a seu.
8,,e,,,,,,,,e,,,,,,e,,,,,,,aa _,
uen e, anaiy s.an the.,u tmi con i
seleet doer, performed af ter the preopera*
tions of the contat:unent or Componeftts. !!
tianal tratage rate test shall be followed DT any, whic!. contributed to the fauure in fg,,q,,s Nest. Ftanea heat shall be est-either a Type A. Type 3. Or Type C test. as meeting the acceptance criterta. Resulta and app: settle for the tres acected ny the modl.
e,&ed usag reactiv;ty and reactor kinetics, analyses of the supplemental vertt$ cation shutdown rescutttles resuittag fross tem.
Acaison. The enessured leakage fresa this test f
shall be included la the report to the Cem.
test employed to demonstrate the validity of peratures and voeds shall be given taetr y
mission. requtred by VA The acerptance erl.
menu minimum WWWe values, ladustag allow M useenMa for the rasgo W pew
(
teria of 111.A.3.th). Eft.aJ or I!!.CJ. no dastribuuem shapes and peaking fasters in.
approprsate shall be met. Stanor modifica.
r (Seca.103.104.1814tl.133. as Stat. Dad. 937.
dacated to be studied above. mod trty and to.
i uans. replacements, or recenting of seal.
948. 964, as amended: 43 UTC. 3133, 3134, earuon may be essessed if they are calculated rtided doors, performet etrectly prior to m 3301(19. 2233) (38 FR 4383. Feb.14.1973: 30 to oscur.
c3nduct of a scheduled Tpe A test da not FR 3087. Mar. S.1973; 41 F14,16447. Apr.19,
- 3. Doesy of Aestaddes. The heat from the recutre a separate test.
1970]
radianctive
- decay of estaaldes, taeludtag 3 afvistple seeksF' berrier er eabermes.
septunta and plutonsum generated dustasr pietrie contanaments. The prtenary remeter opersuoa. as weit as testepes of urmatum. s aba11 he calculated la with fuel I'
tentatnment barrier of a stulttple barrier er cyme amiculatless and kaosa redteactive substmospherte eDatainmeat aball be sub" properties. The acttande doesF heat chosen [
peted to Trpe A toets to,ertly taas its lenk*
Shan De that syproprinto for the time in the age rate meets the restuirements of this nP*
fust erule thma riends the htsbest ennenlaced pen (.1F_ Clher structures of mutuple barrter guel tempermeuse durtag the 14CA.
of auta*Lloopherte contatamenta de g. ese*
- 4. Fiestest Predasst Desap. '!he hea& gen.
endary cantataments for Deillag water seec*
erstacarates from reatteneuve desay of Saalen t att and shield bulletags for pressurteed products shan be assumed to be equal to 1.3 water reactors that encloes the estare primary times the Talasse for todatte operettag time reacter cor.tainment of peruana Oefeef t la the A358 S**a mad (Proposest Amersona i
ahall be subjeet to lsdtvidual teste in assere.
g,egen, n =nesy Standsede rDossy Emergy ance with the precedures spec 18ed la the Release Rasse Petteerung Skuteswa' of techsteal spec!Scauona or assectated bases
- Creatum-Peeled 'Zinerman Reesteen". Ap.
V. : meno. 4 Recomme T=m, preeed try su,ttee. octoba,1.,a. Ales Stand.
ANb a,d, c_
- 13. The trae.
A. Confessment intpertion. A generat in.
Staa of the locally generated games energy spe:tten of the acceemble Intersor and este.
that to depostted ta the feet (tactudtag the raar surf acts of the e$ntainment structures aladdlag) may be dif? prest froga 3.0; the and componenta snalt be performed prior to enlue used shall bo {usttRed by a castable any T)?e A test to uncover any evidence of emiculattom.
structurni d.ierioration which mar airect
- s. aferaseirerer steerete asse. 733. rat.
either the contaanment structurma lategrity of energy retenas. hydrogen generauen. and or leak +Ligittness. If there la evidence of eteddlag saldat&en from the metal / water 30 etructural deteriorettoa. Type A testa saW1 actica aball be calculated using the Baker.
Just equatloa (Baker.1 Just.1 C." Studies not be performed until corr,oettve acuan is of metan water seactices at nigh Therpers.
taken tr eetoedaSee.iut re att prwedurse.
nondestructive esamtriations, and teste as Strres. IIL Espertmental and Theoretteal spec' Set in the applicable code specLSed 18 Studies of the Etreastem Water Remetten."
l 80 Saa at the commencrment of repast AN1e4540, page 7. May 1982). The reaction work. Seth structural eeterioratten and cor.
shall be nasumed not to be steam itmited. Ftr y
rective settens takest shall be rep 3rted as rests when, claddtag ta calculated to rupture part of the test rrport, submitted sa secorti.
durtag the 14CA the taelde of the claddtag ance m eta V.S.
^
shall maes he eseumed to react after the rup.
tm. The cateulause of the runstles umas on esuch tr.eervlee inspecuens are requires DF 8 304aa.
Aenended 38 FR $997.
Pane Re9. 3 of 32 - 5/16/78 50 -37
. - ~=.
---~ - - - - - - - - - - " -
^~
~
- f. l- $rr,<,
Appendix B.5 I
t
("
Procedure No.1-2 THP-4030.STP.202 REY.* '
1-5105 Flow Diagram 2-5105 Check Off Sheet No. Main Steam Da*c.ription II.RT Page 1 of 26 Date Valve No.
Description Open Closed Initial Remote Operated Valves:
MRV-213 S/G #1 Power Operated Relief
/
x MRV-223 S/G #2 Power Operated Re11ef
/
x MRV-233 S/G #3 Power Operated Relief
/
x MRV-243 S/G #4 Power Operated Relief
/
x DCR-310 S/G #1 Blowdown Isolation
/
x DCR-320 S/G #2 310wdown Isolation x
/
DCR-330 S/G #3 Blowdown Isolation x
/
DCR-340 S/G #4 Blowdown Isolation x
/
Manual Isolation (IRC) l BD-101-1, S/G #1 Shell Drain Isolation x
BD-101-2 S/G #2 Shell Drain Isolation x.
80-101-3 S/G #3 Shell Drain Isolation
.x BD-101-4 S/G #4 Shell Drain Isolation x.
BD-102-1 S/G #1 Blowdown Sample Isolation x
80-102-2 S/G #2 Blowdown Sample Isolation
.x BD-102-3 S/G #3 Blowdown Sample Isolation
.x BD-102-4 S/G #4 Blowdown Sample Isolation x
MS-104-1 S/G #1 Sample Test Point. Isolation x
l MS-104-2 S/G #2 Sample Test Point Isolation
.x.
Ms-104-3 S/G #3 Sample Test Point Isolation x.
MS-104-4 S/G #4 Sample Test Poir.t Isolation
.x.
5/16/78
O Appendix B.5 Procedure fo*.1-2 THP-4030 STP.202'Rev. 2 Check Off Sheet No. Main Steam i
Description ILRT Page 2 Date Valve (to.
Description Open Closed Initial MS-105-1 S/G #i Sample Test."oint Isolation x
MS-105-2:
S/G #2 Sample Test Point Isolatic9 x
MS-105-3' S/G #3 Sample Test Point Isolation x
MS-105 S/G #4 Sample Test Point Isolation x
BDX-110 S/G #1 Press Test Point l
x BDX-120 S/G #2 Press Test Point x
- BDX-130 S/G #3 Press Test Point x
BDX-140 S/G #4 Press Test Point x
Manual Isolation (ORC)
B l-1 Blowdown Isolation x
BD-103-2' Blowdown Isolat'.cn x
BD-103-3 Blowdown I ziation x
80-103-4 Blowdown Isolation r
x MPP-210 Main Steam Press Xmitter Vent x
MPP-220 Main S' eam Press Xmitter Vent t
x MPP-230 Main Steam Press Xmitter Vent-x MPP-240 Main Steam Press Xmitter Vent x
O m
l 5/16/78
Procedure No. 9-2 THP-4030 STP'.202 REV.
Flow Diagram 1-2-5114A Check Off Sheet No.
NESW Description ILRT Page 4 Date i
[
Valve No.
Description Open Closed ;
Initial i
_ ECR-951 RCP #1 Mot Air Cooler SuoDiv Isolation x
x WCR-945 RCP #1 Mot Air Cooler Return Isolation WCR-955 RCP #1 Mot. Air Cooler Return Isolation x
WCR-952
- RCP #2 Mot. Air Cooler Supply Isolation x
WCR-946 RCP #2 Mot Air Cooler Return Isolation x
WCR-956 RCP #2 Mot. Air Cooler Return Isolation x
'WCR-953 RCP #3 Mot. Air Cooler Supply Isolation
/
x WCR-947 RCP #3 Mot. Air Cooler Return Isolation
/
.x WCR-957 :
RCP #3 Mot. Air Cooler Return Isolation x
/
WCR-954 ~
RCP #4 Mot. Air Cooler Supply Isolation x
/
W.
18 RCP #4 Mot. Air Cooler Return Isolation
/
x WCR-958,.
RCP #4 Mot. Air Cooler Return Isolation
/
x WCR-961 E. Inst. Rm Vent Supply Isolation
.x WCR-962 E. Inst. Rm Vent Return Isolation
..x
- /#
WCR-963 E. Inst. Rm Vent Return Isolation x
I WCR-965 W. Inst. Rm Vent Supply Isolation
.x
/
i WCR-966 W. Inst. Rm. Vent Return Isolation x
y l
l WCR-967 W. Inst. Rm Vent Return Isolation x-l l
i Manual Isolation (IRC) 1 l
NSW-254-1 CUV #1 Drain Isolation x-1 l
NSW-254-2 CUV #2 Drain Isolation x-l NSW-254-3 CUV #3 Drain Isolation x-N,
.54-4 CUV #4 Drain Isolation x-5/16/78
_ _ _ _ _ -. _ - =.
~
Procedure N212THP-4030 STP.
Appendix B.5 FLOW DIAGRAM l-2-5114A Check Off Sheet No. NESW DOscription ILRT Pace 5 Date
(
Valve No.
Description Open Closed,
Initial NSW-393-1 CUV #1 Drain Isolation x
NSW-398-2 CUV #2 Drain Isolation x
NSW-398-3' CUV #3 Drain Isolation x
NSW-398,4-CUV #4 Drain Isolation x
NSW-403 RCP #1 Motor Air Cooler Drain Isolation l
x NSW-403-2:
RCP #2 Motor Air Cooler Drain Isolation x
NSW-403-3; RCP f3 Motor Air Cooler Drain Isolation x
NSM-403-4i RCP #4 Motor Air Cooler Drain Isolation x
NSW-375-1 RCP #1 Pbtor Air Cooler Vent Isolation x
NSW-375-2 RCP #2 Motor Air Cooler Vent Isolation x
NS i-3 RCP #3 Motor Air Cooler Vent Isolation x
NSW-375.-4 RCP #4 Motor Air Cooler Vent Isolation x
MSW-397-2 RCP #2 Motor Air Cooler Drain Isolation l
'x NSS-374-1 RCP #1 Motor Air Cooler Drain Isolation
' ' x' i
NSW 374 2 RCP #2 Motor Air Cooler Drain Isolation x
NSW-374-3 RCP #3 Motor. Air Cooler Drain Isolation x
n 4SS-374-4 RCP #4, Motor Air Cooler Drain Isolation x
SW-376-1 RCP #1 Motor Air Cooler Vent Isolation I
x-SW-376-2 RCP #2 Motor Air Cooler Vent Isolation x
SW-376-3 RCP #3 Motor Air Cooler Vent. Isolation
[
x NSW-376-4 RCP #4 Motor Air Cooler Vent Isolation x
NSW-236-3 W. Inst. Rm Vent Drain Isolation x-NSW-236-4 E. Inst. Rm Vent Drain Isolation
-x-Designates Unit 2 Only 5/16/78
,.,-,,p y.----
_--,-,n--m,,---.
..,,.ee na,
.-.e_...,, -.
~
~
Appendix B.5 Procedure NoIl2 THP'4030 STP.202* RQ.2_
Check Off Sheet No.
NESW Dascription ILRT Pace 6 Date
[
l Valve No.
Description Open,
closed Initial l
i Manual Isolation (ORC)
~
NSW-414-1' CLV #1 Test Conn.
x NSW-414-2' CLY #2 Test Conn.
x
~
NSW-414 CLV #3 Test Conn.
x NSW-414-4:
CLV #4 Test Conn.
x NSU-212-1 CLV #1 Test Conn.
x NSW-212-2,
CLV #2 Test Conn.
x I
NSW-212-3,
CLV #3 Test Conn.
x NSW-212-4 ',
CLV #4 Test Conn.
x N3W-400-1' CLV #1 Vent Isolation x
ES' 1-2 CLV #2 Vent Isolation x
mr-NSW-400-7' CLV #3 Vent Isolation x
NSW-400-4 CLV #4 Vent Isolation NSW-420-1 CLV #1 Drain Isolation
"'x' NSW-420-2 CLV #2 Drain Isolation x
NSW-420-3 CLY #3 Drain Isolation x
NSW-420-4 CLV #4 Drain Isolation x'
NSW-252-1 CUV #1 Test' Conn.
x-NSW-252-2 CUV #2 Test Conn.
x NSW-252-3 CUV #3 Test Conn.
x 45W-252-4 CUV #4 Test Conn.
.x
.e NSW-386-1 CUV #1 Vent Isolation x
- e NJ"'96-2 CUV #2 Vent Isolation r
en NSn a86-3 CUV #3 Vent Isolation i'
er NSW-386-4 DUV #4 ' Vent Isolation X
- Designates Unit 2 Only 5/16/78
Appendix B.5 Procedure FIo.1-2THP-4030 STP.202 REV'.2_._,
Check Off Sheet No.
NESW Description ILRT Page 3 Date Valve flo.
Descriptien Open Closed Initial Remote Operated Valves:
WCR-901 CLV #1 Supply Isolation
/
x WCR-902 CLV #1 Return Isolation x
WCR-903 -
CLV #1 Return Isolation I
[
x BCR-905 CLY #2 Supply Isolation
/
x WCR-906 CLV #2 Return Isolation
/
x WCR-907 CLV #2 Return Isolation
/
I x
WCR-509 CLV #3 Supply Isolation
.x
/
UCR-910 ',
CLV #3 Return Isolation x
/
WCR-911 CLV #3 poturn Isolation x
/
W 3
CLV #4' Supply Isolation
/
x WCR-91.4 s-CLV #4 Return Isolation x
WCR-915 CLV #4 Return Isolation x
WCR-921 CUV #1 Supply Isolation x-
'/
WCR-922 CUV #1 Return Isolation
/
x WCR-923 CUV #1 Retur.n Isolation x
/
WCR-925 CUV #2 Supply Isolation x
/
WCR-926 CUV #2 Return Isolation
[
.x.
WCR-927 CUV #2 Return Isolation
/
x WCR-929 CUV #3 Supply Isolation x
/
l WCR-930 CUV #3 Return Isolation
/
x WCR-931 CUV #3 Return Isolation x.
/
1 Wr" 433 CUV #4 Supply Isolation
'x'
(
Wt..
.r34 CUV #4 Return Isolation x~
WCR-935 CUV #4 Return Isolation x
5/16/78
Appendix B.5 Procedure Ho*.12THP-4030 STP.202REV. 2 FLOW DIAGRAM 2-5114 A Check Off Sheet No.
NESW Description ILRT Page 7 Date Valve No.
Description Open Closed,
Initial
-u
'tNSW-399-1 CUV #1 Vent Isolation 4
- NSW-399-2 CUV #2 Vent Isolation x
"*NSW-399-3 CUV #3 Vent Isolation x
- NSW-399-4 COV #4 Vent Isolation x
NSW-422-1 CUV #1 Drain Isolation x
NSW-422-2 CUV #2 Drain Isolation x
'NSW-422-3, CUV #3 Drain Isolation x
NSW-422-4..
CUV #4 Drain' Isolation x
NSW-241-1:
RCP #1 Motor Air Cooler Drain Isolation x
NSW-241-2:
RCP #2 Motor Air Cooler Drain Isolation x
N 11 - 3:
RCP #3 Motor Air Cooler Drain Isolation x
NSW-241-4' RCP #4 Motor Air Cooler Drain Isolation x
NSW-242-1 RCP #1 Motor Air Cooler Drain Isolation x
NS'.i-242-2 RCP #2 Motor Air Cooler Drain Isolation
,x-j NSW-242 RCP #3 Motor Air Cooler Drain Isolation x
l NSW-242-4 RCP #4 Motor. Air Cooler Drain Isolation x
NSW-243-1 RCP #1 Motor Air Cooler Drain Isolation x-NSW-243-2 RCP #2 Motor Air Ccoler Drain Isolation x-NSW-243-3 RCP #3 Motor Air Cooler Drain Isolation x
NSW-243-4 RCP #4 Motor Air Cooler Drain Isolation x
NSW-387-1 RCP #1 Motor Air Cooler Vent Isolation x
' hSW-387-2 RCP #2 Motor Air Cooler Vent Isolation x.
NSW-387-3 RCP #3 Motor Air Cooler Vent Isolation x
h.
a87-4 RCP #4 Motor Air-Cooler Vent Isolation x-
- Designates Unit 2 Only 5/16/78
=
e Appendix 8.5 Procedure NoJ2 THP 4030 STP.202 REVl2 FLOW DIAGRAM 1-2-5114A check Off Sheet No.
NESW Description ILRT Page 8 Date Valve No.
Description Open Closed Initial NSW-416-3 W Inst. Rm Vent Test Conn.
~
x NSW-416-4 E Inst. Rm Vent Test Conn.
x "NSW-388-3 W Inst. Rm Vent Vent Isol x
- %SW-388-4 E Inst. Rm Vent Vent Isol
~
x
'%SW-377-3 W Inst. Rm Vent Vent Isol x
"%SW-377-4!
E. Inst. Rm Vent Vent Isol x
'NSW-421-3.
W Inst. Rm Vent Drain Isol x
NSW'421-4 E Inst. Rm Vent Drain Isol
.x
~#
NSW-234-31 W Inst. Rm Vent Drain Isol x
- NSW-234-4!
E Inst Rm Vent Drain Isol x
7
-.l.
i
[
t i
i
- Desianates Unit 1 only
- Designates Unit 2 only l
l l
5/16/78 1
. ~..
Appendix B.5 Procedure NY.12 THP-4030 STP.202 REV12 1
FLOW OIAGRAKS: 12-5115A/12-51188 Check Off Sheet No. Primary Water /
Description ILRT Page 9 Date 2 &H h ht.
2 Valve No.
Description Open,
Closed,
Initial Manual Isolation (IRC)
DW-213(-215 _ Hose Conn. for Refuel Cavity Scrubdown x
DW-214(-21'6 bseConn.forRefuel.Cavityscrubdown x
SEE NOTE BELOW Manual Isolation (ORC)
DW-209(-21:1, Manual Isolation x
DW-210(-21.2; Manual isolation x
DW-207(-20;8 Manual Drain Isolation
~
x DW-295' Manual Isolation x
.j Manual Isolation (ORC)
N-122(-113)
No to Accumulators x
_N-150(-144)
N2 to PRT
'x N-T49(-145)
Np to RCDT
x' GPC-320 Sensing Line for GRV-320
- x NOTE: Where identical Unit 'l and Unit 2 valves have different unique Identification Numbers. Unit 2 Numhart are down in parentheses.
- Designates Unit 2 only l
5/16/78
,-n-
,, - - - ~ ~ - -,
,,-,--,------,-.->,,-,,,r
-,,r-g.-,,,.--a, - =
,-n.,,.
-..-w,-
-,-+._aw,
--,,..,,e-.n-,u,,,.,--,-
m-
O' Appendix B.5 ProcedureNI.32THP4030STP.202~REV 2 FLOW DIAGRAM: 12-51208 l,
Check Off Sheet No. COMPRESSED AIR Description ILRT PAGE 10 Date i
1 Valve flo.
Description Open Closed,
Initial kemote Operated Valves XCR-100 Control Air to Containment y
x XCR-101 Control Air to Containment x
I XCR-102 Control Air To Containment x
XCR-103
. Control Air to Containment h
~ ~
x Manual Isolation (IRC)
XPA-101 Control Air to Containment Press Alarm Vent x
~
XPA-104 I
Control Air to Containment Press Alarm Vent x
PA-145(-243,)
Plant Air to Containment Isolation x
~
i TSEENOTEBELOW C
Manual Isolation (ORC) l CA-170 Control Air To Containment Isolation
'x CA-171 Control Air To Containment Isolation
x' XPX-100 Control Air To Containment Test Isolation
~ x KPX-110 Control Air To Containment Test Isolation
' x CA-172 Control Air To Containment Test Isolation x
CA-173 Control Air To Containment Test Isolation
'x' PA-144(-239)
Plant Air to Containment Test Conn.
~
x NOTE: Where identical Unit 1 and Unit 2 valves have different unique Identification Numbers, Unit 2 numbers are shown in parentheses.
5/16/78 4
..r-m r,
.e,,----,m, e------~w-
,n
,--er.w.swa
.am e--em---
-w,-,--..-w..-
,--n.--+-e
,..--.w.,-
,-.n,--
,. ~, - ~ ~.. - -
Appendix 8.5 Procedure No.12-THP-4030 STP.202 REV:2 FLOW DIAGRAMS: 1-2-5124/1-2-5137A~
Check Off Sheet tto. Station Drainage /
kus vents a uratns i
Description ILRT PAGE 11 Date Valve No.
Description Open Closed,
Initial Remote Operated Valves DCR-600 Containment Drains to Dirty Waste Isol.
x DCR-601 '
Containment Drains to Dirty Waste Isol.
x DCR-201 RCDT to Vent Header Isol.
x DCR-203 RCDT to Vent Header Isol.
/
~'
1 x
DCR-202 RCDT to Gas Analyzer Isol.
/
x
'DCR-204 RCDT to Gas Analyzer Isol.
l y.
/
1 DCR-205 RCDT to RCDT pps. Isol.
.x
/
DCR-206 '
/
x DCR-207 N2 to RCDT Isol.
/
x i
DM-GIO Ice Condenser Drains to Clean Waste
[
x i
DCR-611 v Ice Condenser Drains to Clean Waste x.
[
DCR-620 Cont. Vent Unit Drains to Clean Waste x
DCR-621 r,gnt. Vent Unit Drains to Clean Waste
"/
x-Manual Isolation (IRC)
UD-249 Refueling Cavity Drn. to RCDT Isol.
x-WD-250 Refueling Cavity Drn to RCDT Isol.
x-WD-251 RCOT to Gas Analyzer Vent x-I WD-252 RCDT to Gas Analyzer Iscl.
x WD-254 RCDT to Vent Header Isol.
x l
UD-255 RCDT to Vent Headef* Isol.
- x...
l, 5/16/78
.. _._ _ __ __ _. _.~ _ _ _ _,. _,
= -. _ _ _
Appendix B.5 Procedure No.1?THPO 30 STP.202'REV f" ~ '
j FLOW DIAGRAMS: 1-2-5124/1-2-5137A Check Off Sheet No. STATION DRAINAGE /
WDS VENTS & DRAI!!5 Description ILRT PAGE 12 Date Valve No.
Description Open closed Initial i
r Manual Isolation (ORC)
DR-121 Containment Drains to Dirty Waste Test Conn.
x DR-122 '
Containment Drains to Dirty Waste Test Conn.
x DPX-600 -
Containment Drains to Dirty Waste Test Conn.
x DPX-201 -
.RCDT to Vent Header Test Conn.
x I
DPX-203 :
RCDT to Vent Header Test Conn.
x
' DPX-202 RCDT to Gas Analyzer Test Conn.
x
. - _ ~
DPX-204 RCDT to Gas Analyzer Test Conn.
x DPX-205
2 x
i DPX-206 RCDT to RCDT pps Test Conn.
l x
D*
Wl N2 to RCDT pps Te:t Conn.
x DPX-208s-RCDT to Refueling Water Purification pps Test Conn.$
x DPX-210 RCDT to Refueling Water Purification pps Test Conn.:
x SF-159 RCDT to Refueling Water Purificatio'n pps Test Isol.
x-
~
SF-160 RCDT to Refueling Water Purification pps Test Isol.
x-DPX-610 Ice Cond Drains to Dirty Waste Test Conn.
x i
(
DPX-620 Ice Cond Drains to Dirty Waste Test Conn.
x
!!D-271 Ice Cond Drains to Dirty Waste Test Conn.
x-WD-272 Ice Cond. Drains to Dirty Waste Test Conn.
x WD-275 Ice Cond. Drains to Dirty Waste Test Conn.
x WD-276 Ice Cond. Drains to Dirty Waste Test Conn.
x 1
d 4
5/16/78 i
~
Appendix B.5 Procedure No*.*l2 THP-4030 STP.202 'REV.2 FLOW DIAGRAM: 1-2-5128A
~
Check Off Sheet No.
RC System Description ILRT PAGE 13 Date Valve No.
Description Open Closed initial Remote Operated Valves RCR-100 PRT to Gas Analyzer Isol.
x RCR-101 PRT to Gas Analyzer Isol.
x GCR-301 Np to PRT Isol.
/
x NCR-252 Primary Water to PRT
/
x DRV-1 PRT drain x
Manual Isolation (IRC)
S1-188 ECCS Reliefs to PRT Test Conn.
x NPX-300 N2 to PRT Test Conn.
x N
'l N2 to PRT Test Conn.
x PW-276 Primary Water To PRT Isolation x
CS-440-1 Seal Water Injection RCP #1-Test Conn.
x CS-440-2 Seal Water Injection RCP #2 Test Conn.
x-CS-440-3 Seal Water Injection RCP #3 Test Conn.
x CS-440-4 Seal Water Injection RCP #4 Test Conn.
x CS-443-1 Seal Water Injection RCPfl Isolation
-x CS-443-2 Seal Water Injection RCP #2 Isolation
.x CS-443-3 Seal Water Injection RCP #3 Isolation x'
CS-443-4 Seal Water Injection RCP #4 Isolation x
RC-124 Pressurizer '!ent x
WD-238 PRT Vent x-9 5/16/78
Appendix B.5 Procedure No.12THP 4030 STP.202 REVJ2 FLOW DIAGRAM: 1-2-5128A Check Off Sheet No. RC System Description ILRT PAGE 14 Date i
Valve No.
Description
' Open Closed Initial Manual Isolation (ORC)
NPX-151 Pressurizer Instrumentation Dead k'eight Calibration :
x PW-272 PW to PRT Isolation x
PW-273 PW to PRT Test Conn.
x PW-274 PW to PRT Test Conn.
x NPX-251 P" to PRT Test Conn.
x NOTE: The PW to PRT line between PW-272 and PW-27d should be drained per TP-3 GPX-311 Np to PRT Test Conn.
x GPX-301 Np to PRT Test Conn.
x d
PRT to Auto Gas Analyzer Test Conn.
x I
NPX-100 '
PRT to Auto Gas Analyzer Test Conn.
x i
NPX-101 PRT to Auto Gas Analyzer fast Conn.
x 5/16/78
Appendix B.5 Procedure N6*12.rup antn gro gsg 'eEY'.?
FLOW DIAGRAMS: 1-2-5129/1-2-5129A Check Off Sheet No.CVCS-Rx tetanwn &
Dascr1ption ILRT PAGF 15 Date i
Valve No.
Description Open Closed.
Initial
~
Romnte onarated valv c OCR-300 Letdown Isolation x
i QCM-250 RCP Seal Water Return Isolation x
QCM-350 RCP Seal Water Return Isolation x
e Manual Isolation (IRC)
'CS-320 Charging Line Test Conn.
x CS-475 RCP Seal Water Return Isolation
.x Manual Isolation (ORC)
QF 3
Letdown Line Test Conn.
x CS-400 '-
RCP Seal Water Return Drain Isol. -
x QPX-351 RCP Seal Water Return Test Conn.
x-e 4
S W
O 5/16/78
i
^#"
Procedure No.12 THP 4030 STP.202 REV'.2 FLCW DIAGRAMS: 1-2-5135 & 1-2-5135B
~
Check Off Sheet !!o.
CCW 4
Description ILRT PAGE 16 Date Valve No.
Description Open Closed,
Ir.itial Retr.ote Operated Valve.s CCM-458 CCW to RCP Themal Barrier & B' abino Clrs.
e x
CCM-459 '
CCW to RCP Thermal Barrier & Bearing Clrs.
x i
CCM-453 -
CCW from Bearing Coolers I
f x
CCM-454 CCW from Bearing Coolers
~
x x
CCM-451 CCW from Thermal Barrier
'CCM-452 CCW from Thermal Barrier
~
[
x CCR-455 CCW to Rx Support Cooling
~
x
/
CCR-456 ',
CCW from Rx Support Cooling
/
x l
CCR-457 '
CCW from Rx Support Cooling x
/
CCR f42 CCW to Excess letdown Hx
/
x CCR-460 -
CCW from Excess Letdown Hx x
CCR-440 CCW from CPN-3 & -4 Cooling Coils x
CCR-441 CCW from CPN-2 & -5 Cooling coils x-CCM-430 CCW to CEQ-1
/
x
+
CCM-432 CCW to CEQ-2
-x
/
CCM-431 CCW from CEQ-1 x
l CCM-433 CCW from CEQ-2
.x.
/
1 Manual Isolation (IRC)
CCW-320 CCW to RCP Thermal Barrier & Bearing Clr: Vent x
CCW-327 CCW to RCP Themal Barrier & Bearing Clr: Vent x-l 5/16/78 e
a w
,,,,.,,-w,-,
--s-n---+-..--v,-
--,.,w-,av-,-e,-.
-,.m
-,m--
4, - -,
,.-,,a-
.,e,,,.-,~-n,--,,m,.,
AppGndix B.S ProcedureNo**12THP4030STP.202.E FLOW DIAGRAMS: 1-2-5135 & 1-2-51358 Check Off Sheet No. CCW Dr
'ption ILRT PAGE 17 Date Valve No.
Description Open Closed,
Initial CCW-332-1 CCW to Lower Bearina Cooler Vent RCP #1 r
{
_CCW-332-2 CCW to Lower Bearina Cooler Vent RCP #2
~
r CCW-332-3 CCW to lower Bearino Cooler Vent RCP #3 x
CCW-332-4*
CCW to Lower Bearing Cooler Vent RCP#4 x
CCW-331 CCW from Thermal Barrier & Bearing Cooler Vent x
CPX-451 CCW to Rx Support Cooler #1 Test Conn.
x CPX-452 CCW to Rx Support Cooler #2 Test Conn.
x CPX-453 CCW to Rx Support Cooler #3 Test Conn.
x CPX-454 CCW to Rx Support Cooler #4 Test Conn.
x CPT ~41 CCW to Rx Support Cooler #1 Test Conn.
x l
PA..,2 CCW to Rx Suppor't Cooler #2 Test Conn.
x i
CPX-463 CCW to Rx Support Cooler #3 Test Conn.
x CPX-464 CCW to Rx Support Cooler #4 Test Conn.
x CPX-456 C'CW from Rx Support Cooler #1 Test Conn.
.x -
CPX-457 CCW from Rx Support Cooler 12 Test Conn.
i CPX-458 CCW from'ix SuDDort~ ooler_ #3. Test 2no r
~
- PX-459 CCW from Rx Support Cooler #4 Test Conn.
r CPX-466 CCW from Rx Support Cooler il Test Conn, r'
' :PX-467 CCW froin Rx Support Cooler #2 Test Conn, x
- PX-468 CCW from Rx Support Cooler #3 Test Conn.
x CPX-469~
CCW from Rx Support Cooler sa T et ra..
x CCW-337-25 CCW to CPN-3 & -4 Vent Isolatten r
337-72 CCW to CPN-2 & -5 Vent Isolatiori
'x CCW-338-25 CCW from CPN-3 & -4 Vent Isolation x
CCW-338-72 CCW from CPN-2 & 5 Vent Isolation x
5/16/78
Appendix B.5 Procedure No22 THP-4030 STP.202 REV 3 FLOW DIAGRAMS: 1-2-5135 & 1-2-5135B Check Off Sheet No. CCW Dr
'ption ILRT Page 18' Date l
Valve No.
Description Opan Closed,
Initial CCW-320-25 CCW to CEQ-1 x
CCW-320-72 CCW to CEQ-2 x
CCW-319-25 CCW from CEQ-1 x
CCW-319-72 CCW from CEQ-2 x
Manual Isolation (ORC)
'CCW-121 CC'i to Thermal Barrier & Bearino Clrs' Drain v
CCW-132 CCW from Bearing Cirs Test Conn.
'x i
CCW-133 CCW from Thermal Barrier Test Conn.
x Cr '14 CCW to Rx Support Cooling Test Conn.
x CCh-40 CCW from Rx Support Cooling Test Conn.
~
x CCW-141 CCW to Excess Letdown Hx Drain x
CPX-450 CCW to Excess Letdown Hx Test Conn.
Y CPX-460 CCW from Excess Letdown Hx Test Conn.
x CCW-241-25 CCW to CPN-3 Cooling Coils x-1 CCW-241-72' CCW to CPN-5. Cooling coils x
CCW-242-25 CCW to CPN-4 Cooling Coils x
CCW-242-75 CCW to CPN-2 Cooling Coils x-i
[
l l
4/2/80
Appendix B.5 FLOW OIACR/F.S: 12-5136/1-2-5146B/1-2-5147A Procedure flo32 THP4030 STP.202 REV.3 SFP Ccoling ICE Cond Check Off Sheet fica Cleanuo
. Refricer
/ Aux. Bldg' tion Dr iption ILRT PAcr 19 ~
Date Ventila tion 4
Valve No.
Description Open Closed Initial Remote Operated Valves VCR-10 Glycol to AHU's x
VCR-11 Glycol to AP'J's
[
x VCR-20 Glycol from AHU's
/
x VCR-21 Glycol from AHU's x-VCR-101 Inst. Rm Purge Supply Isol.
x VCR-201 Inst. Rm Purge Supply Isol x
VCR-102 Inst. Rm Purge Exhaust Isol.
x VCR-202 Inst. Rm Purge Exhaust Isol
/
x VCR-103 Lower Cont. Purge Supply Isol
[
x VCn 203 Lower Cont. Purge Supply Isol x
VCR-104 Lower Cont. Purge Exhaust Isol.
x VCR-204 Lower Cont. Purge Exhaust Isol.
/
x VCR-105 Upper Cont. Purge Supply Isol
' x~
VCR-205 Upper Cont. Purge Supply Isol
/
x
/
VCR-106 Upper Cont. Purge Exhaust Isol.
x' VCR-206 Upper Cont. Purge Exhaust Isol.
v VCR-107 Co.nt. Press Equalization Isolation v
VCR-207 Cont. Press Equalization Isolation x'
ECR-31 Air Particle / Radio Gas Detector f enlatinn v
ECR-32 Air Particle / Radio Gas Detector Isolation x
ECR-33 Air Particle / Radio Gas Detector X
I s
I a
t 4/2/80
-_,,,,--,,..-r-
.--,,,.----,,w
-,--,rv,v--,yw,,,---y-,,,-y-,
..v--,
i Appendix B.5
~
~
Procedure flo.12 THP 4030 STP.202 RrV. 3 FLOW DIAGRAMS 12-5136/1-2-5146B/1-2-5147A SFP Cooling / Refri Check Off Sheet flo.& Cleanuo
/ Aux. Bldg,/
tion i
Dr iption ILRT PAGE 20 Date
/ Ventilation Valve flo.
Description Open Closed Initial Unit 2 Valves in nar.n m a.eManual Isolation (ORC)
SF-151( 52) Refuelino Water to Refuelina Cavity v
SF-153(-154) Refueling Water to Refuelino Cavity v
RPX-153(-15 %) Test Connection between SF-152 k -154 x
VPX-201 Inst. Room Purge Supply Test' Conn.
x VPX-202 Inst. Room Purge Exhaust Test Conn.
x VPX-203 Lower Cont. Purge Supply Test Conn.
x VPX-206 Upper Cont. Purge Exhaust Test Conn.
x VPX-207 Cont. Pressure Equalization Test Conn.
x SM S Air Particle / Radio Gas Sample Isolation x
SI.
Air Particle /Rallio Gas Sample Test Conn.
x SM-4 Upper Volume Grab Sample Isolation x
SM-5 Upper Volume Grab Sample Test Conn.
x-SM-6 bpper Volume Grab Sample Isolation
'x SM-8 Lower Volume Grab Sample Isolation x
SM-9 Lower Volume Grab Samole Test Conn.
x SM-10 Lower Volume Grab Sample Isolation x
SM-12 Air Particle / Radio Gas Portable Sample Isol.
x VPX-204 Lower Cont. Purge Exhaust Test Conn.
x y
VPX-205 Upper Cont. Purge Supply Test Conn.
x 4/2/80
- * ~
App:hdix B.5 FLOW DIAGRAMS: 12-5141,12-5141A & 1-2-51418 Check Off Sheet ?!o. NUCLEAR SAMPLING Dr
'ption ILRT PAGE 21 Date Valve tb.
Description Open Closed,
Initia'.
l Remote Operated Valves S1] Wu r}
ICR-5 Accumulator Samole Isolation (Nue. Camnlinn Dnnm) '
'r
~
i l
ICR-6 Accumulator Sample Isolation x
l NCR-105 Hot Leg Loops 1 & 3 Isolation-x NCR-106 Hot Leg Loops 1 & 3 Isolation I
x l
NCR-107 Pressurizer Liquid Sample Isolation" x
NCR-108 Pressurizer Liquid Sample Isolation" x
i NCR-109 Pressurizer Steam Sample Isolation "
.x NCR-110 Pressurizer Steam Sample Isolation "
x i
MCP 151
~
S/G #1 Steam Sample Isolation x
~
- k..a2 S/G #2 Steam Sainple Isolation x
MCR-253
S/G #3 Steam Sample Isolation x
MCR-254 S/G #4 Steam Sample Isolation x'
DCR-301 S'/G #1 Blowdown Sample Isolation
~ x DCR-302 S/G #2 Blowdown Sample Isolation x'
i DCR-303 S/G #3 Blowdown Sample Isolation x-DCR-304 S/G #4 Blowdown Sample Isolation x
ECR-10 H2 Sample Isolation (Local Panei) lei'L Oe* k e
'x ECR-20 H2 Sample Isolation x'
ECR-ll H9 Sample Isolation r
ECR-21 Hp Sample Isolation x
ECR-12 Hp Sample Isolation r
.2 Hp Sample Isolation x'
5/16/78
'ECR-13 Hy emmnt. t'e nt m Jnn a
a v
,ECR-23 H2 Sample Isolation X
. Appendix-B.5' FLOW DIAGRAMS: 12-5141,12-5141 A, & 1-2-5141B Check Off Sheet No. NUCLEAR SAMPLING ILRT PAGE 22 Date Dr
'ption Valve No.
Description Open Closed Initial ECR-14 H3 gamn1 nnlaunn x
ECR-24 x
ECR-15 x
[
ECR-25 x
ECR-16 x
ECR-26 x
ECR-17
~
x ECR-27
.x ECR-18 x
ECD-?8 x
Et
.9 x
ECR-29 x
i 6
Manual Isolation (ORC)
IPX-5 Accumulator Sample Test Point x
IPX-6
' Accumulator. Sample Test Point x
l NPX-105 Hot Leg Loops 1 & 3 Sample Test Point x
NPX-106 Hot Leg Loops 1 & 3 Sample Test Point x:
NPX-107 Pressurizer Liquid Sample Test Point x
NPX-108 Pressurizer Liquid Sample. Test Point x
NPX-109 Pressurizer Steam Sample Test Point x
NPX-110 Pressurizer Steam Sample Test Point x.
e N S/16/78
,,,,r-
--,,,-------r---
,---,--------------r-,-,-----,---
Appendix B.5 FLOW DIAGRAMS: 12-5141, 12-5141 A, 1-2-5141 B Procedure No.12 THP 4030 STP.202 R N.2 Check Off Sheet No. NUCLEAR SAMPLIf[G ption ILRT PAGE 23 Date Dr ' '
Valve No.
Description Open Closed Initial i
EPX-11 H7 Sample Test Conn.
_l x
EPX-12 x
EPX-13 x
EPX-14 x
EPX-15 x
EPX-16 x
EPX-17 x
EPX-18 x
EPX-19 x
NC '70
' H Sample Header Isolation, x
2 Nd.66 H Sample Header Vent x
2 NS-256 H Sample Pump A Inlet Isolation -
2 x
NS-257 H2 Sample Pump B Inlet Isolation x
NS-253
'H Sample Return Isolation
'x '
2 NS-326 H2 Sample Return Vent
-x-t 5/16/78
,w.
--2--,--.3.
,,. - - -.. ~ - - - - -.. -.
.,w
..-,.--.-y
.. < ~
-w.---.,..-----,-w.-
. - - -, -. - - - -. -,,.., - -,, - - - - - ~. - -
_s.
Appendix B.5 FLOW DIAGRAM: 1-2-5142 Procedure No.12 THP 4030 STP.202' REV.2_ ;
Check Off Sheet No. ECCS (SIS)
De
'ption ILRT PAGE 24 Date Valve No.
Description Open Closed Initial Remote Ooerated Valves 7
ICM-250 Hioh Head S.I. Isolation to looes
/
X b'
ICM-251 High Head S.I. Isolation to Loops
(-
x ICM-260 Low Head 5.1. Isolation to.L' oops 1 & 4 f.5 ' ^
.Y x
st
/.
ICM-265 Low Head S.I. Isolation to Loops 2 & 3 GV x
Manual Isolation (ORC)
IPX-253 High Head S.I. Test Conn.
x IPX-254 High Head S.I. Test Conn.
x S' ' '7 High Heat S.I. Flushing Line Isol.
x Si 25 High Head S.l.' Flushing Line Isol.
x Sl-ll8N s-Low Head S.I. to Loops 1 & 4 Test Conn.
x Sl-120N Low Head S.I. to Loops 1 & 4 Test Conn.
x S1-1185
' Low Head S.I. to Loops 2 & 3~ Test Conn.
_x -
S1-120S Low Head S.I. to Loops 2 & 3 Test Conn.
x-
- IPX-260 Low Head S.I. to Loops 1 & 4 Test Conn.
x
- IPX-265 Low Head S.I. to Loops 2 & 3 Test. Conn.
x
- Designates Unit 1 Only e'
l 5/16/78 l
T
.. - _.~
Appendix B.5 FLOW DIAGRAM: 1-2-5143 Procedure No.12THP-4 nan sTo sn? dry _3_
Check Off Sheet No. Eccs (q99)
Ds
'ption ILRT PAGE 25 Date Valve No.
Description Open Closed Initial Remote Ooerated Valves ICM-305 East RHR Rectre. Sump Isolation x
ICM-306 West RHR Recire. Sump Isolation x
ICM-129 RHR from Loop 2 Hot Leg Isolation
/
3 x
ICM-311 Low Head SI to Hot ' Legs Isolation x
ICM-321 Low Head SI to Hot Legs Isolation x
~
/
l3 ICM-lll RHR to cold legs Isolation x
GCR-314 N2 to Accumulators Isolation x
i.E _
O :- s r -,
Manual Isolation (IRC)
N 71
- a g-,
RH-131 RHR to Cold Legs Vent.
82 x
IPX-102 Np to Accumulators Test Conn.
r x
-m eq em Manual Isolation (ORC)
TJ 9 y sm S1-194 SI Test Line Isolation ic
-hi '
l S1-1 71 SI Test Line Isolation x'
S1-172 SI Test Line Isolation
'x' GFX-314 N2 To Accumulators-Test Conn.
m
~x RH-130 RHR to RWST Isolation x
I 4/2/80 i
t
~.
' Appendix B.5 Procedure No.**12 THP 4030'STP.202 Rev.;
FLOW DIAGRAM 1-2-5145 & 1-2-5145A Check Off Sheet tio. enn+
o r g +,., + g., t e
Weld Channel.
Dtse-iotion ILRT PAGE 26 Date p,....,, 47,t4cn Valve (to.
- Description Open Closed ;
Initial Ramnto Anarated Valvoc
_ PS0-250 Zone 1 Air 9unniy Ten 1ation
/
v PS0-251 Zone 3 Air Sunolv Isolation v
/-
b x'
PSO-255-Zone 2 Air Supply Isolation M
l PS0-256 Zone 4 Air Supply Isolation x
Man 0a1 Isolation (IRC)
CA-l'83 Zone 2 Main Header Test Conn.
x CA-196 Zone 1 Main Header Test Conn.
x CA '92 Zone 2 Main Header Isolation x
C,.
s5 Zone 1 Main Header fsolation x
CA-266 e Z6ne 3 Main Header Test Conn.
x Zone 4 Mai~ Header Test Conn.
x-
~
CA-308 n
e a
N G
1 6
b e
5/16/78 9
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- 12 THP 4030 STP.202 Sheet 1 of 1 E.2 PRESSURIZATION DATA SHEET #1 Rev. 2 - 5/16/78 UPPER CONTAINMENT PRESSURE'S I
DATE TIttE Rufi #
PU-l PU-2 INITIAL i
won
- Sm l
l l
i
.=
1 DATA RE\\ IEWED BY
/
_.-_.,...___.e.,. _... _,., _. -. _. -.
- 12 THP 4930 STP.202 E.2 PRESSURIZATION DATA SHEET #2 Sheet 1 of 1 e.
- 5/16/78 LOWER CONTAINMENT PRESSURES I
DATE TIME RUN #
PL-1 PL-2 INITIAL l
l
(
l l
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/
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- 12 THP 4030 STP.202 Shest 1 of 1 E.2 PRESSURIZATION DATA SHEET #3 Rev. 2 -'5/15/78 ICE CONDENSER. PRESSURES AND ATMOSPHERIC PRESSURE
/
DATE TIME RUN #
PI-l PI-2 PATM INITIAL l
l l
l l
DATA REVIENED BY
/
n
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-n_.
n-.,,.n-_,
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DATA REVIWED BY
/
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- 12 THP 4030 STP.202 Sheet I of 1 E.3 STABILIZATION DATA SHEET #1 Rev. 2 - 5/16/78 UPP.ER CONTAINMENT PRESSURES DATE TIE RUN #
PU-l PU-2 INITIAL 4
s s
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DATA REVIEWED BY
/
~_-
E.3 STABILIZATION DATA SHEET #2 sk; 1oO 0 m.M.?
1 6/78 LOWER CONTAINMENT PRESSURES DATE TIME RUN #
PL-l PL-2 INITIAL 9
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/
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- 12 THP 4030 STP.202 Shtet 1 of 1 E.3 STABILIZATION DATA SHEET #3 Rev. 2 - 5/16/78 ICE CONDENSER. PRESSURES AND ATMOSPHERIC PRESSURE DATE tit 1E RUN #
PI-l PI -2 FATM INITIAL 0
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DATA REVIEWE] BY
/
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- 12 THP 4030 STP.202 E.3 STABILIZATf0N DATA SHEET #4 Sheet 1 of 1
~
TIMEKEEPER'S RECORD AND AiSIENT TEliPERATURE EXACT TIME OF AMBIENT DATE DATA COLLECTION RUN #~
TEMPERATURE INITIAL
~
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l t
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e f
l l
DATA RINIEWED BY
/
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/
l
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2 - 5/16/78 LOWER CONTAINMENT PRESSURES
/
DATE TIME RUN #
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/
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DATE TIME RUN #
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/
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E.4 TIMEKEEPER'S RECORD AND AMBIENT TEMPERATURE EXACT TIME OF APEIENT DATE DATA COLLECTION RUN #
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\\
i DATA REVIEED BY
/
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- 12 THP 4030 STP.202 E.5 SUPPLEMENTAL TEST DATA SHEET #1 Shett 1 of 1 Rev. 2 - 5/16/78 UPPER CONTAINMENT PRESSURES
/
DATE TIME RUN #
PU-l PU-2 INITIAL mum T
4 6
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/
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- 12 THP 4030 STP.202 E.5 SUPPLEMEf4TAL TEST DATA SHEET #2 t
2 - 5/16/78 LOWER C0TiTAINf4Et4T PRESSURES
_/
DATE TIME RUN #
PL-1 PL-2 INITIAL D
l l
DATA REVIEWED _BY
/
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I NOTE: This is a Unit 2 sketch I
Unit 1 similar.
5, I
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Ref. dwg. 1-5581 8 2-5581 C Rev. 2 5/16/78 l
+
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- 12 THP 4030 STP.202 Sh et 1 of 2 APPENDIX C.2 SUPPLEMENTAL, TEST INSTRUMENTATION INSTALLATION SKETCHES c 14W (2LL*-37')
2 9" -
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i I
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i Ref. Dwg. 1-5581 B 2-5581 C Rev. 2
~
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2-5581C Rev. 2 5/16/78 i
- 12 THP 4030 STP.202 l,
~~
Sh et 2 of 2 APPENDIX C.2 SUPPLEMENTAL TEST INSTRUMENTATION INSTALLATION SKETCHES FLo w R E G ui.A TiH G-V(-)LNE "V-1" V
M..--
~
eson ;
8' CONTA/NMEW7 i <
$UFPLEMENML TEST g
. ' # *~d
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l PRESsuez 'ina.vsmirice PPP-302 t
~
l Rev. 2 5/16/78 4
t I
f
oo.
- 12 THP 4030 STP.202 Sheet 1 of 3 APPENDIX D.1 TYPE C LEAKAGE PENALTY FORM Type C Leakage Penalty for Undrained Systems:
ISOLATION LEAKAGE DESCRIPTION CPN#
VALVES (scem)
RCDT to RCDT pps 40 DCR-205 DCR-206 RC System accumulator fill lines 68 ICM-265 Refueling water line to Refueling Cavity 36 SF-151 SF-153 3
Cont. Sump Line to Waste Hold up Tanks 41 DCR-600 DCR-601 NESW to and from Containment (see tabu-lation on D.1 sheet 2 and 3
_RCP Seal ' ater Lines 11 CS-442-1 W
12 CS-442-2 43 CS-442-3 14 CS-442-4 CVCS letdown and excess letdown lines 34 QCR-300 37 QCM-250 & 350 Samples Lines from Accumulators 81 ICR-5 ICR-6 Sample Lines from Pressurizer 66 NCR-109 & 110 l
NCR-107 3108 3
CYCS Chargina Line 35 CS-321 Glycol lines to and from ice condenser 86 YCR-10 & -11 AHU's 56 VCR-20 & -21 Tots 1 Type C Leakage =
Penalty (scem)
Expressed in % La
=
La = 110,220.74
%La = Total Type C Leakage Penalty : La 0
~ _ _ - - -..
. = _ _ _ _ _.-.
t
- Isolation Leakage Valves (SCCM) ety gg 17 WCR-901 21 WCR-902 17 NSW-415-1 21 WCR-903 18 WCR-905 4
22 WCR-907 CLV #2 i
18 NSW-415-2 22 WCR-906 19 WCR-909 23 WCR-910 CLV #3 19 NSW-415-3 23 WCR-911 20 WCR-913 24 WCR-914 CLV #4 20 NSW-415-4 24 WCR-915
(
26 WCR-921 26 WCR-923 CUV #1 26 NSW-419-1 26 WCR-922 27 WCR-925 27 WCR-927 CUV #2 l
27 NSW-419-2 27 WCR-926 85 WCR-929 85 WCR-931 CUV #3 85 NSW-419-3 85 WCR-930 l
Rev. 3 4/2/80 i
Yalves (SCCM) 84 WCR-933 84 WCR-935 CUV #4 84 NSW-419-4 84 WCR-934 i
26 WCR-945 26 NSW-244-1 RCP #1 Motor Air Coolers 26 WCR-951
{
26 WCR-955 27 WCR-946 27 NSW-244-2 RCP #2 Motor Air Coolers 27 WCR-952 27 WCR-956 i
85 WCR-947 85 NSW-244-3 RCP #3 Motor Air Coolers 25 WCR-953 65 WCR-957
,f 84 WCR-948 84 NSW-244-2 RCP #4 Motor Air Coolers l
84 WCR-954 84 WCR-958 73 NSW-417-4 73 WCR-962 E. Inst. Room Vent 73 WCR-961 73 WCR-963 73 NSW-417-3 73 WCR-966 l
W. Inst. Room Vent l
73 WCR-965 73 WCR-967 Total NESW System Type C Leakage =
l l
Rev. 3 4/2/80
- 12 THP 4030 STP.202 Sheet 1 of 5 APPENDIX D.2 INSTRUMENT CALIBRATION AND CERTIFICATION SUM 4ARY FORM PRESSURE INSTRUMENTATION Manufacturer Model Range input output S/N TE#
DATE OF CALIBRATION /RECAL PUI PU2 4
PL1 PL2 PIl PI2 PATM Calibration Data and Documentation Attached
/
DEW POINT HYGR0 METERS Manufacturer Model Range input output S/N TE#
DATE OF CALIBRATION /RECAL VPUI VPU2 VPL1 VPL2 VPIl l
I VPI2 Calibration Data and Documentation Attached
/
Rev. 2 5/16/78
. ~ - -,.,., - - - - -,,,..,,,, - - -,
,-n-
-n
-,c,,
,,me-
.--r.,-.
-,-,.,,,,--,, - -,e
~
- 12 THP 4030 STP.202 Sheet 2 of 5 CONTAINMENT TEMPERATURE MONITORING SYSTEM Manufacturer Model Upper Volume Temp. Range ETR-S/N l
l l
i a
f Rev. 2 5/16/78
m12 4030 STP.202 Sheet 3 of 5 1
Lower Volume Temp. llange ETR-S/N i
i e
e l
1 I
l I
l Rev. 2 5/16/78 l
i -
~.
0o12 THP 4030 STP.202 Sheet 4 of 5 ETR-
$/N Ice Condenser Temp. Range ETR-S/N
(
Calibration Data and Documentation Attached.
/
Data Aquisition Systems and Processing.
Note: The system (s) used for Data Aquisition may vary from test to test.
TEMP. DATA AQUISITION Manufacturer Model Range input output Calibration D(ta and Documentation Attached.
/
Rev. 2
'/16/78
~.
- 12 THP 4030 GTP.202 Sheet 5 of 5 PRESSURE DATA AQUISITION (IF AUTCMATED)
Manufacturer Model Range input output Calibration Data and Documentation Attached
/
MACHINE INTERFACING (IF AUTOMATED)
Manufacturer Manufacturer Model Model Function:
Function:
Documentation Attached
/
SUPPLEMENTAL TEST EQUIPMENT Pressure Gage Manufacturer Model Range Serial Number TE - #
Calibration Data and Documentation Attached
/
FLOWMETER r
Manufacturer Model Range l
Serial Number TE #
l Calibration Data and Documentation Attached
/
4 I
Rey, 2 5/16/78
\\
The conversion is based upon the following criteria.
(1)
The relationship between MV and CF is linear
- 0F = MV (K11) + 0 (K11 p 0) or affine 0F = MV (K11) + K12 (K11'K12 / 0)
(2)
The conversion function used does not degrade the accuracy of the temperature measurement beyond acceptable limits.
(3)
A single equation represents all of the RTD's located in its associated compartment.
If any of the above 3 criteria cannot be met, a modification will have to be made to the data analysis program, or recalibratica of the RTD bridge modules performed. Consultation with AEPSC I & C and Computer applications sections is required before modifying the ILRTEST I
program:
The following instructions shall be followed for properly detemining RTD Conversion Constants and entering them on the Fixed Information Coding Form.
(1)
Obtain Calibration data for all of the RTD-bridge modules used for this test.
/
(2)
Verify that the criteria listed above has been satisfied.
/
(3)
Use the calibration data to detemine the conversion formula for the RTD's in each compartment.
/
F=MV(Kg1)+XM2 M = 1, 2, 3 l
M = 1. Upper Compartment RTD's M = 2, Lower Compartment RTD's M = 3. Ice Condenser RTD's NOTE: The data could be entered into the P-250 curve fitting program (ref. "P-250 Operator's Console l
Reference Manual for Nuclear Power Plant Super-vision" W TP-044P) for a first order curve fit detemination.
Page 1 of 10 Rev. 2 - 5/16/78 I
~.
- +12 THP 4030 STP.202 (4)
Record the values determined in (3) above on line Al of the Fixed Informaticn Data Coding Form found in D.3.6 of this Appendix.
/
K Cols. 1-6 K12 --+ Cols. 7-12 jj
- C 2 M ols, 13-18 K22 -
Cols.19-24 K
K31 Cols, 25-30 K32 --, Cols. 31-36 RUN CONTROL INDICES Consult reference 2.12.2, the "ILRTEST" Operations Guide.
Cond. A1: Cols. 41 43 Designate the first computer run number for which it is desired that START data be processed. If left blank, PROCESSING data will be processed from run #1.
Cols. 51-53 Designate the last computer run number for which it is desired that END data be processed. If left blank, PROCESSING program will process all data starting with the start index run number.
Cols. 61-63 Designate first computer run for which printed output is desired.
If left START blank, program will print only the PRINT last data run.
All three of these indices may be left blank initially but as the test progresses circumstances will warrant selection of new indices.
D.3.2 DATA CARDS B1 - B3 HYGROMETER CALIBRATION CONSTANTS These constants are required by the ILRT Computer Programs to convert the mill'.vott (MV) outputs from the containment humidity l
instruments to the Dew point" temperatures (OF) the signals represent.
The conversion is based upon the following criteria.
(1)
The relationship between (MV) and (OF) 2 is quadratic
- 0F = MV (Lj1) + MV(L12) + L13 or affine
- Li1 = 0 (2)
The conversion function used does not degrade the accuracy of the dew point measurement beyond acceptable limits.
(3)
A single equation describes the functional relationship of one humidity instrument.
If any of the above 3 criteria cannot be met, a modificatior.
will have to be made to the data analysis program, or recalibration of l
the humidity instrument affected performed. Consultation with AEPSC
((/b6h8 i
't.
The following instructions shall be followed for properly detemining the Hygrometer Calibration Constants and entering them on the Fixed Information Coding Fem.
(1) Obtain calibration data for all of the Hygrometers.
/
(2) Verify that the criteria itsted above has been satisfied.
/
(3) Use the calibration data to determine the conversion formula for each Hygrometer.
/
'F=MV2(Lal)+MV(Lm2)+Lm3 M 1, Upper Cont. Hygrometer #1 M=2, Upper Cont. Hygrometer #2 M=3, Lower Cont. Hygrometer #1 M=4, Lower Cont. Hygrometer #2 M=5, Ice Cond. Hygrometer #1 M=6, Ice Condl Hygrometer #2 NOTE: Use the P-250 curve fitting program for a second order curve fit determination.
(4) Record the values determined in (3) above on lines B1-B3
(.
of the Fixed Infomation Data Coding Form found in D.3.6 of this Appendix.
/
Line B1 L11 + Cols. 1-10 L12 -* Cols.11-20 L13 --+ Cols. 21-30 L21
- Cols. 31-40 L22 + Cols. 41-50 L23 - -+ Col s. 51 -60
(
Line B2, B3 Similar to above for lower and ice condenser, i
D.3.3 DATA CARDS C1 - C7 MANOMETER CALIBRATION DATA These constants are required by the ILRT Computer Program to correct manometer readings according to their calibration data. This is done by placing in the program the True Pressure and Quartz Manometer Readings as determined from calibration data on the manometers for a pressure range from approximately 28 psia to 26 psia.* The program accepts 5 sets of data, starting with the highest pressure and descending to the lowest pressure in the required pressure range. The program uses the data to perfom double interpolations to detemine corrected pressure output for given pressure inputs.
- Except PATM which is in the range from 15-13 psia Page 3 of 10 Rev. 2 - 5/16/78 I
-,_...--. ~... - _.. -.
. - - - - ~. -
= _ -.
_ - _ = _ _._
- 12 THP 4030 STP.202 The nature of this program requires that the following criteria be met:
(1) Five data sets are available approximately in the range specified.
(2) Data are in PSIA.
The following instructions shall be followed for properly detemining Manometer Calibration Data and entering them on the Fixed Information Data Coding Form.
(1) Obtain calibration data for all of the manometers.
/
(2) Verify that the criteria above has been satisfied.
/
(3) Complete lines Cl through C7 of the Fixed Information Data Coding Form as follows:
i For Upper Cont. Manometer #1:
C1, W1 Cols. 1-8, Enter the highest true pressure value in 28-26 psia range.
(
C1, R1 Cols. 9-16 Enter the corresponding quartz manometer l
reading.
Cl, W2 Cols. 17-24 Enter the second highest true pressure value.
C1, R2 Cols. 25-32, Enter the corresponding QM reading.
Repeat for C2 through C7 C2 Upper Cont. Manometer #2 C3 Lower Cont. Manometer #1 C4 Lower Cont. Manometer #2 i
C5 Ice Condenser Manometer #1 C6 Ice Condenser Manometer #2 C7 Atmonspheric Pressure Manometer. For Card C7 data is entered on the 13-15 psia range.
I l
D.3.4 DATA CARDS D1 - DS RTD WEIGHTING FACTORS l
RTD weighting factors are factors which divide each of the three containment compartments into the volume fractions being represented by individual RTD's. The volume being represented by a particular RTD i
is detemined by the location of the RTD and the division of the volume I
in closest proximity to it as a function of uniform temperature distribution Page 4 of 10 Rev. 2 - 5/16/78 4
a-
~.v
,,-,,-w
-~
-,,,re, m
w,,
,,-,-m-,.,
,,-m,v--.
,-,--n,-r
--n.
n=-,, - - --.. - - - -,. - --
i Ref. 2.11.2, AEPSC Calculation #12-PI-04, contains information required to detemine the RTD weighting factors for the Unit 1 and 2 containments. The weighting factors are calculated in 'per unit' using each compartment's (Upper, Lower, Ice) net free volume as the base value for all the RTD ' Representative Volumes' in each compartment.
In 12-PI-04, the Upper and Lower Volume RTD weighting factors are calculated for two containment configurations.
(1) Reactor Missile Shields in their normal positions to the side and above the refueling cavity above the reactor head.
(2) Reactor Missile Shields removed from their nomal positions so as to allow access to the reactor head.
In Case (1) the volume above the reactor head enclosed by the missile shileds is part of the lower volume and the temperature of this volume is represented by ETR-113.
In Case (2) the volume above the reactor head is in much closer 1
connunication with the Upper Volume, and ETR-113 represents not only that volume that would normally be enclosed by the missile shields l
but also a portion of the volune that in case (17 was being represented entirely by ETR-114.
These are the only two containment configurations that are nomally encountered in performing the ILRT that affect RTD weighting factors.
If the containment were modified in any manner that would affect the net free containment volume or distribution of that volume, or RTD's were added and/or relocated, the RTD weighting factors would have to be recalculated to reflect this new situation.
The ice condenser cc:npartment weighting factors present a special case. The net free volume is a function of the ice displacement.
l The most recent ice basket weights must be taken into account to accurately determine the ice ccndenser RTD weighting factors.
The following instructions shall be followed for properly detemining the RTD conversion constants and entering them en the Fixed Information Data Coding Form.
(1) Verify that no containment modification has been performed or no special conditions exist that would affect the net free volume of the upper and lower containment volumes or the volume distribution relative to positions of containment RTD's.
/
NOTE:
If conditions are such that RTD weighting factors must be recalculated AEPSC I&C section must be notified to perfonn the engineering analysis of the new conditions.
Page 5 of 10 Rev. 2 5/16/78
- 12 THP 4030 STP.202 (2) Determine the position of the Reactor Missile Shields as being either in position over the reactor head (Case 1) or rencved from the nomal position so as to provide access to the head.
(Case 2)
Case (1)
/
'"~
Case (2)
(3) Enter RfD weighting factors on lines 01 through D4 of the Fixed Information Data Coding Form for the applicable containment configuration.
Card F.TR RTD Weighting Factor Cols.
Case (1)
Case (2) 01 101 0643
.0628 1-6 D1 102
.1188
.1161 7-1?
01 103
.0850
.0831 13-18 Upper D1 104
.0850
.0831 19-24 D1 1 05
.0983
.0960 25-30 Volume D1 106
.0983
.0960 31-36 01 107
.0983
.0960 37-42 RTD's 01 108
.0983
.0960 43-48 D1 109
.0303
.0296 49-54 D1 110
.0303
.0296 55-60 D2 111
.0303
.0296 1-6 D2 112
.0303
.0296 7-12
(
D2 114
.1047
.0740 13-18 D2 128
.0107
.0105 19-24 02 133
.0171
.0167 25-30 D2
.113 LEAVE BLANK
.0513 31-36 D3 122
.0395
.0415 1-6 D3 123
.0395
.0415 7-12 D3 124
.0395
.0415 13-18 D3 125
.0395
.0415 19-24 D3 126
.0097
.0102 25-30 D3 127
.0270
.0284 31-36 D3 129
.0557
.0586 37-42 D3 130
.0082
.0086 43-48 Lower D3 131
.0253
.0266 49-54 D3 132
.0557
.0586 55-60 Containment 03 134
.0986
.1037 61-66 D4 135
.0986
.1037 1-6 RTD's D4 136
.0986
.1037 7-12 D4 137
.0986
.1037 13-18 D4 138
.0476
.0500 19-24 D4 139
.0088
.0092 25-30 D4 140
.0232
.0244 31-36 D4 141
.0138
.0145 37-42 D4 142
.0162
.0170 43-48 D4 143
.0236
.0249 49-54 D4 144
.0208
.0219 55-60 Da 145
.0228
.0240 61-66 D4 146
.0402
.0423 67-72 D4 113
.0490 LEAVE BLANK 73-78 Page 6 of 10 Rev. 2 5/16/78
~
Average Basket Weight
/
(excluding weight of basket itself)
Date Weighing Completed (5) Determine the amount of volume displaced in the total ice bed volume by the amount of ice indicated above.
Vice = ice disp 1 gement (ft ) = 1944 (# of ice baskets) 3 T6 [\\
x Av. Basket Weight /lbm i x1 1bm basket /
Vice =
ft 3
/
(6) Determine the ice bed free volume Vice bed = 129,057.4 - V ce =
ft 3 i
/
(7) The ice bed free volume is represented by three RTD's:
ETR-119. ETR-120, and ETR-121 They represent slightly different sized volumes given by the following equations 7
\\
ETR-119 = fVice bed X 94 V
Ygy, + 10,877.20 =
{
(
f' VETR-120 " Vice bed x 117.5
(
299.6 + 13,595.50 =
3 V
VETR-121 *i ice bed 5 + 10.182.90 =
L (8) Complete the following table:
RTD Weighting Representative ETR Factor Volume 115 11,948.5 116 11,948.5 117 11,556.5 118 11,556.5 119 VETR-ll9 "
120 VETR-120 =
121 VETR-121 =
TOTAL 1.0000 Page 7 of 10
$2/80
_. _ ~ -
- 12 THP 4030 STP.202 f
(Weighting Factor)ETR*= (Representative Volume)ETR.* * (Total Representative Voim?)
(9) Enter the RTD weighting factors detemined above on Line D5 of the Fixed Infonnation Data Coding Form as follows:
i ETR Cols.
115 1-6 116 7-12 117 13-18 118 19-24 119 25-30 l
120 31-36 121 37-42 D.3.5 DATA CARD El VOLUME WEIGHTING FACTORS Volume weighting factors are factors which divide the Net Free Containment Volume into upper, lower, and ice condenser volume fractions. The volume fractions are expressed in per unit based upon the Net Free Volume of the lower containment. The factors are used in the ILRT analysis program to " weight" the influence of pressure, temperature and vapor pressure changes occurring in each of the 3 volumes as a function of the relative size of the volume.
In this manner the migration of the original mass of air in each volume into adjoining, volumes or out of the containment is datermined. This is known as a 3 compartment analysis.
Reference 2.11.3, AEPSC Calculation 12-PI-05, contains the information required to determine the volume weighting factors for the Unit 1 and Unit 2 containments. As in D.3.4 of this Appendix, the following additional information must be known.
(1 Piacement of Reactor Missile Shield (2
Average Ice Basket Weights (3
Modifications, if any, that would affect the Net Free Volume in the containment or distribution of the volume.
NOTE: If conditions are such that the volume weighting factors must be recalculated, AEPSC !aC section must be notified to perfom the engineering analysis of the new conditions.
The following instructions shall be followed for properly determining the Volume Weighting Factors.
(1) Placement of. Reactor Missile Shield Case (1)
(Ref. D.3.4)
/
Case (2)
(Ref. D.3.4)
VeV. % *' '
5/16/78
k I
InTEcAPGEb t.EPIK PshTE TEST P A(i E._
O F i
I DATA t
D. c. ct UNIT HTE --
t
- 12 THP 4030
..".202
..r
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ni., + n n + + c es
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i3c0 UPPER' L
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/ '////U ////UHJ ///)///////>
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,i,. uta g Page 10.of'10 D.3.6 FIXED INFORMATION DATA CODING FORM
. Rey, '2 5/16/7e' l
L
- 12 THP 4030 STP.202 (2)
V ce =
(Ref: D.3.4)
/
i (3) Determina the Net Free Ice Condenser Volume Vg = 210,723 - VICE BED (Ref: D.3.4) 3 (ft)
=
(4) Complete the following ta'le:
o 1
Lower Volume Base (ft )
Volume Weighing Factors l
3 JU >er Lower Ice Case (1) 365,614
- 1. IBT3 T.DT60 Case (2) 349,467 2.0144 1.0000 Weighing Factor for Ice Condenser = VI t (Lower Volume Base) Case *
(5) Complete Line El of the Fixed Information Data Coding form as follows:
l Cols.
Lower Volume Weighing Factor TT Upper Volume Weighting Factor 8-14 Ice Condenser Weighting Factor 15-21
(
i Page 9 of 10 Rev. 2 - 5/16/78
~
- 12 THP 4030 STP.202 APPENDIX D.4 SUPPLEMENTAL TEST FLOW STANDARDIZATION Flow measured using the Brooks Flowmeter in the Supplemental Test must be corrected to standard conditions using the following fannula:
4h T Ncorr " Nind t
x 14.
Where:
W
= Corrected volume flow or air in SCFM corr Winj = Fiow indicated by ficwmeter P
= Pressure indicated by Heise Gage t
P,,
= Atmospheric Pressure T
= Temp for volume where bleed line originates When setting initial flow rate for the Supplc4nental Test, read P P. T and W and determine W Adjust the throttling of thN10w t
ind corr.
meter to get W AS CLOSE TO 3.0 SCFM as possible.
corr Record P,g, P, T, and W g
ind every i hour.
(
REFEENCE CCPy Omy NO REVISIONS TO DE ISSUED i
Page 1 of 1 l
Rev. 3 4/2/80
=,
- 12 THP 4030 STP.202 Sheec 1 of 1 APPENDIX E
- DATA SHEETS E.1 ILRT DATA CODING FORM The form is attached. More can be obtained by calling AEPSC Computer Division and refering to form CA-262-1.
Note that ETR-113 appears on the form twice, once on the Upper Containment Temp. Card T2 and once on the Lower Cont. Temperature Card T4.
Enter ETR-ll3 on T2 when the Reactor Missile Shields are not in place.
Enter ETR-ll3 on T4 when the Reactor Missile Shields are in their normal operating position.
Leave the "other" space provided for ETR-113 blank.
- NOTE: These data sheets are used only if appropriate Auto Data Aquisition Equipment is unavailable.
i l
Rev. 2 - 5/16/78
i
- 12 THP 4030 STP.202 APPENDIX B.1 INSTRUMENT VENTING LIST PAGE I The following Instruments, located within the Containment should be protected from damage which could result from a pressure differential or pressure above atmospheric in accordance with Prerequisite 3.2.6.
INST. NO.
DESCRIPTION VERIFIED BY 4
QDA-010 (PT-153)
RCP 1 No. 1 Seal-DP Cell QDA-011 (PT-149)
RCP 1 Therm. Barr-DP Cell QDA-020 (PT-152)
RCP No. 1 Seal - DP Cell QDA-021 (PT-148)
RCP 2 Therm. Barr - DP Cell QDA-030 (PT-151)
RCP 3 No 1 Seal - DP Cell QDA-031 (PT-147),
RCP 3 Therm. Barr - DP Cell QDA-040(PT-150)
RCP 4 No. 1 Seal - DP Cell QDA-041 (PT-146)
RCP 4 Therm. Barr - DP Cell f
i 3
NFA-210 (FIS-417 Loop 1 Temp Manifold flow DP GA/ Switch NFA-220 (FIS-427)
Loop 2 Temp Manifold - DP GA/ Switch NFA-230 (FIS-437)
Loop 3 Temp Manifold - DP GA/ Switch NFA-240 (FIS-447)
Loop 4 Temp Manifold - DP GA/ Switch
'l e
3 i
Rev. 3 4/2/80
- 12 THP 4030 STP 202 APPEN0!X B.1 INSTRUMENT VENTING LIST
/
PAGE 2 INST. NO.
DESCRIPTION VERIFIED BY QFI-010(FIS-165)
RC PPI Seal by-pass FL Rotam with SW QFI-020(FIS-164)
RC PP-Seal By-Pass FL Rotam with SW QFI-030(FIS-163)
RC PP3 Seal By-Pass FL Rotam with SW QFI-040(FIS-162)
RC PP4 Seal By-Pass FL Rotam with SW g
l l
l
{
Rev. 3 4/2/80 w.
,.--n.
.n.-------,.,
n-.,
n.
- 12 THP 4030 STP.202 APPENDIX B.1 INSTRUMENT VENTING LIST g-PAGE 3 INST. NO.
DESCRIPTION VERIFIED BY C0A-451 RCP 1 Thermal Barrier DP C0A-452 RCP 2 Thermal Barrier DP CDA-453 RCP 3 Thermal Barrier OP C0A-464 RCP 4 Thermal Barrier OP QFR-10 RCP 1 Seal Bypass Flow QFR-11 RCP 1 Seal Bypass Flow QFR-20 RCP 2 Seal Bypass Flow QFR-21 RCP 2 Seal Bypass Flow QFR-30 RCP 3 Seal Bypass Flow QFR-31 RCP 3 Seal Bypass Flow QFR-40 RCP 4 Seal Bypass Flow I'
QFR-41 RCP 4 Seal Bypass Flcw I
t Rev. 3 4/2/80
'~
~
Ref. Dwg. 5115A D/7
/
hnb hf s
System Draining Sketches Drain for Unit 1 l
Sheet 1 of I ILRT
.j:
Drain encircled piping uun ns sections as free of':.te U
Uk e
"'],y (e as possible.
Initial
~
=
JD* giu.rs' M
and date when completed.
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+
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s ae bwe, E3" r +'"
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- ~*~
h r
t Drain for Unit 2 ILRT r -
c,l w
- - r c
i
.~ -. ~ J?.,., --
YJ Ref. Dwg. 5128 C/9
/
W,i d:.;- -r, = :. et m,.
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ga g
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==- f L Sell'elC CLA%% 11 pg 7
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Cf.XNNMM Sgt One.5437&,OTm Ref. Dwg. 5137A M/9
/
fu !
-f8I T
IS 5.sme tuitavute.ftfisse 49#
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5/16/78 i
l m12 THP 4030 STP.Ir>
Sheet 1 of 2 i
- =
Appendix B.3 M, Q System Venting Sketches s
i N*
RCR-iol
[ _
. W.W es Tent Pressurizer Relief Tarik oj h
by opening valve for NPX-300 f-A N^
GCR-ho\\,
" t t.
.t g
Ref. dwg. 1-2-5128A B/9
/
FRESSoRitfa MLICF TANK g
p I
Vent Reactor, Coolant yo gi Drain Tank by opening f
hWD-251 v
)
wo en DcR-202
\\
gsac oa coeu~r Ref. dwg. 12-5137A D/S 7'
para ass k
_k "*~ 's' RC824 y h uno-ist
---?
nmo-1"3 Pre s.wceseg Vent Reactor Coolant System by opening RCl24 s
NJ Ref. dwg. 1-2-5128A J/7
/
Q R.d.S.
l Rev. 2 5/16/78
^^f2 IM 3020 SI' 202~ --
App [nhixB.'3 I
Sheet 2 of 2
-.s; 44.I SI ICA-2 l
g*
SI IG4 3 Vent each Accumu15 tor s: sp.4 Tank by opening S1-164 "I
/
i SCcomot.aToq Tanks (f)
-2
/
~3
/
Q) f
-4
/
Ref. dwg. 1-2-5143 E/1 I
o 1
4>I I
i Rev. 2 - 5/16/78 l
I 1
i i
g
- 12 THP 4030 STP.202 v
Appendix B.4 Sheet 1 of 2 Pressurized Gas Systems, Venting A'
A 84 Sketches c,m W
D W
D r
(ut, e A,
2, h,
Isolate N2 supply by closing f
(U2 i
i 1
NJ 1
GCR-301 and Q
i
~
W N-150 (Unit 1) y l
N-144 (Unit 2)
GCR-Sol N 157
/' rom cPN-74 2'
Vent Np supply line at PRESsuSer4 Ns Sum:f GPX-31T and NPX-300 R5uu Hrao R 2^'"
Verify NPX-301 is closed 12-51188 Ref. dwgs.1-2-5128A
/
Isolate N2 supply by closing g2p DCR-207 and N-149 (Unit 1)
N-145 (Unit 2) o g
g Vent N2 supply line at GPC-320 1149 -(U1)
DcR 20~7 N too qa5(U2)
Verify DPX-201 and DPX-207
'-Facci
' ;o * 'I
- d i
e a
i
/
N Swee-Y 3 c q 2.o l v
A 0-CPr1-3!j t
Daaw g-eca a-A.
D 12-51188 Ref. dwgs. 1-2-5137A
/
Isolate N supply by closing GCR-314a$d r@
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N-113 (Unit 2) 70 a"Cu.mut.McRS Vent N Supply at GPX-312 3
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12-51188 v
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1 Appendix B.4
- 12 W P 4030 STP.202 Sheet 2 of 2
=
Verify spool piece between flanges has-been removed.
t SLIND ~f.AN6ES Verify blind flanges have PA 145 Ul) been installed.
j P6 743 U2) g
. Verify PA-1 44 and PA-145 j
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are closed (Unit 1) j PA-144 Ulf[-
Verify PA-239 and PA-243 c PN-2'?
are closed (Unit 2)
PA-239 U2) y CormPRE4se D To coa.u e.g.,7 SE 8.V ic 9.S i!
Ref. dwg. 12-51208
/
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/
4 2
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CONTAINMLNT TENPERATUkts DATA CHtC%
UPPER VOLUME LUatd VOLUML RTD MILLI-VOLTS DLG. F.
RTD MILLI-v0LTS DLG. F.
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MILLI-VOLTS ~ "DE G. ~ F. -' " " - ' ~ ~
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_ETH-134 39.72 79.44 h
I. ! ETRalle 39.61 79.22 ETH-136 40.24 80.4H l
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SUMMARY
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2 a
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80.T3 LOWER VOLUML ( Dt b.
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80.66 ICE CONDENSER (DEG. F.)
20.33 3
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540.36 ICE CONDENSER (DEG. R.)
480.03 q
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CONTAINMENT VAPOR PRES 5URE DATA CHtCK CONT A IN.HE_ N_T PRESSU_R.E.S__DA_T A_ _ CMECM _. _. _
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MILLI-DEW POINT V.POR FHL55UNE UNCORRECTED CORRECTED HYGROMETER VOLTS (DEG. F.)
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MANOMETER READING (PSIA) 0:EADING (PSI A)
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14.'36 3 7 - "- ~-
l.3 AVfRAGE VAPUR PRESSURES d
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SUMMARY
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UPPER CONTAlt4 MENT (PSIA) 0.1519
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LOhER CONTAINMfNT (PSIA) 0.163J AVERAGE UPPEP PRESSURE (PSIA) 26.6518 Q-
'l ICE CONDtHSER (PSIA) 0.0499 AVERAGE LokER PRESSURE (PSIA) 26.6260~~--'
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' AVERAGE ICE ~CONDFNSER'~ PRESSURE ~lPSIAl-~ 26.6364 AVERAGE CONTAlhMENT FRESSURE (PSIA) 26.6381 s,.
7 AVt H AGE CONT AINME NT PRESSURE IPSIG) 12.2744
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SUMMARY
OF WEIGHTLD AVERAGE TEMPERATUNES r
s' UPPEH VOLUME (DEG. F.)
66.03 LOWER VOLUME (deb. f.)
69.72 ICE CONDENSER (DEG. F.)
17.37 22 UPPER VOLUME (DEG. R.)
525.73 LOWER VOLUME (DEG. R.)
529.42 ICE CONDEh3ER (DEG. R.)
477.07 m
N n
CONTAINMENT VAPOR PRESSURE DATA CMLCK CONTAINHENT PRESE'JRES DATA CHECK M
F FILLI-DEW POINT VAPUR PRtSSukE UNCORRECTED CORRECTED j'
HYGRUMETER VOLIS (DEG. F.)
f VEU-1
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(PSIA)
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SUMMARY
OF CORRECTED AVERAGE PRESSURES a
upper cnNIAltdMENI..f RS1AL n.uJj h f
LdWER CONTAINMLNi (PSIA) 0.0641 AVERAGE UPPER PHESSURE (PSIA) 96.7928 a
ICE CONDENSEH (PSIA) 0.0321 f
AVLHAGE LOWER PHESSURE (PSIA) 26.7836 AVtHAGE-lCE_ CONDENSER _ PRESSURE 4 PSI Al-26.7865----
f AVERAGE CONTAINMENT PRESSURE (PSIA) 26.7877
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AVtHAGE CONTAINMENT PRESSURE (PSIG) 12.42S5
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1.0 INTRODUCTION
[
The second (fir-t periodic) Integrated. Leak Rate Test (ILRT) for the DonaTd C. Cook Nuclear Plant - Unit 1 Reactor Containment was successfully completed on May 29, 1978 by members of the Indiana and flichigan p
Power Company and the k:erican Electric Power Service Corporation.
The ILRT was perfomed as specified in the I&M Surveillance Test Procedure 12-THP 4030.STP.202 Rev. 2.
American National Standard - ANSI-N45.4-1972
" Leakage Rate Testing of Containment Structures for Nuclear Reactors", and Code of Federal Regulations 10 CFR 50 Appendix J " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors" were used as guidelines for ti.e procedure and for the associated leak rate calculations. The absolute test method was used on the 3 compartment containment model developed for both the Unit 1 and Unit 2 preoperational Integrated Leak Rate Tests.
Data collected over a 14 hour1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> period every half hour was used to calculate the nomalized weight of the initial dry air mass remaining in the containment. The measured Typ' A leakare rate, Lam, is the slope of a straight line detemined fres a linear least-squares fit of the calculated nomalized weight vs. cice.
Following the 14 hour1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> test, a 71/2 hour supplemental test was perfomed by imposing a known leakage on the containment, measuring i
the composite leakage, and comparing it with the results with Type A leakage to verify the accuracy of the leakage measurements.
2.0 INTEGRATED LEI.K RATE TEST ACCEPTANCE CRITERIA As per FSAR Section 5.2.1 and Unit 1 Technical Specifications, the containment allowable leabge, La, is defined as 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a pressure Pa (12.0 psig). The measured leakage rate, Lam, must be demonstrated to be less than 0.75 La, (0.1875 %wt/ day) as required by 10 CFR 50 Appendix J.
In addition, the accuracy of the leakage measurement must be verific:1 by perfoming a supplemental test, the results of which are acceptable provided the difference between the supplemental test results and the Type A test results is within 0.25 La (0.0625 %wt/ day).
As specified in Section 5.0 of D. C. Cook Plant Surveillance Test Procedure 12-THP 4030.STP.202 and in accordance with 10 CFR 50 Appendix J Section III A," Leakage Test Requirements, Type A Tests",
the test was considered acceptable when the following had been verified:
Page 1 e
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2.1 The leak rate, as determined by the 95% upper confidence limit of the least squares ime, Lam /95%, has converged to an acceptable level:
Lam /95% <(0.75 La - Type C Leakage Penalty) 2.2 The duration of the Type A Test has exceeded the minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the difference between the 95% upper con-fidecce limit of the leak rate, Lam /95%, and the leak rate itself, Lam, is less than 0.25 La:
(Lam /95% - Lam)
<0.25 La 2.3 The changes in upper confidence level leakage, Lam /95%,
and the measured leakage, Lam, do not show a negative trend over the last two hours of the test.
The Supplemental Test was considered acceptable when the following had been verified:
2.4 The duration of the Supplemental Test has exceeded the mininum of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2.5 The sum of the imposed leak, Lo, and the leakage measured during the ILRT, Lam, is within + 0.25 ta of the composite leakage, Lc, measured in the supplemental test:
(Lo + Lam - 0.25 La) < Lc
<(La + Lam + 0.25 La)
The criteria used for this Intergrated Leak Rate Test is more stringent than the Unit i preoperational test criteria and that specified in 10 CFR 50 Appendix J.
These criteria also incorporate additional test commitments made by American Electric Power Service Corporation representatives to the l
Nuclear Regulatory Commission. The additional commitments are embodied in a response to Question 022.14 of Appendix Q of the Donald C. Cook Nuclear Plant Unit 2 FSAR. They were retrofitted to be made applicable to Unit 1 as well as Unit 2.
Additional :riteria were also added to make possible the reduction of the duration of the ILRT test period from a min-imum of P.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to a minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. No existing codes specify a minimum test duration for the ILRT.
The criteria added were added to ensure the ILRT would not be terminated in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the leak rate was converging to an accept-able value and that the number of data sets was adequate to reduce the effects of random errors in the leak rate measure-ment to within 0.25 La.
Page 2 l
3.0 ILRT TEST RESULTS Table 3.1 Leakage Rate Summary Duration of Type A Test: 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Duration of Supplemental Test:
7.'5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> i
i Measured Leakage
- Allowable Leakage
- i-(%wt/24 hours)
(%wt/24 hours) '
{
A.
ILRT ' Type A' L.
Leak Rate, Lam
-0.05686
-0.1875**
S.
ILRT ' Type A' 95%
0.75 La - Type Penalty Leakage +
-0.1875 - (-0.0157)]
=l 0.1718]
Upper confidence limit Leak rate,- Lam /95%
-0.06544
=.. -
I C.
Type C Penalty Leakage
-0.0157 N/A O.
Imposed Leak Rate, Lo
-0.2177 0.5 La ilo < La
= [0.125 <[.q < 0.25],,
E.
Supplemental Test Composite Leakage Lc
-0.30999 N/A i
l, F.
Supplemental Test Lam + Lo - Le l Lam + Lo - Lc l < 0.25 La **
' ~
(-0.2177) -
=[ Lam + Lo - Le l < 0.0625]
'T Correlation
.= [-0.05686 +
{
(-3.0999)]
l-
= [0.0354]
[
- The slope of the linear regression line computed for weight remaining in the containment as a function of time is :tegative since weight l
regaining in the containment decreases as a functicn of time. Hence
~
leakage out of the containment is shown as negative in Table 3.1.
f
- 10 CFR 50 Appendix J test criterion
+ Test criterion specified by plant procedure 12-THP 4030 STP.202, Rev. 2.
++ Guideline leakage proposed in ANS 274 Draft No.1 I
f Page 3 i
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(c) Location (d) Containment Description
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(e) Date Test is Compicted 7.S.3 Technical Data 3
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- M 65/
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(c) Mass step change measure by Type A (d) Test instrumentation 7-10
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' 39. 69 ~~'
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j LIH-145 40.46 o0.96
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I ETH-146 39.50 79.00
. '.I SUMMAHY of wEI6hTED AVER AGE.It.M.PE.H ATOHLs (d
UPPER VOLUME (DEG. F.)
H0.63 LOWE R VOLUME (Dtb. f.)
d0.07 ICE CONDENSfH (DtG. f.)
19.88 UPPER VOLUME (DE G.
R. )
540.33 LOWLH VOLUME (DLb. R.)
539.77 ICE CONDENSER (DEG. R.)
479.58
.) -
f ja liO a
CONTAltJME NT VAP0k PPESSURE DAT A CPLCK i;
, CONTAINMENT PHESSURES_ DATA CHECa:
a MILLI-DEW POINT VAP0H ekt SSUNL
.{
HYGkOMETER VOLTS (DEG. F.)
(PblAl i
UNCORRECTED COHRECTED VPU-l
-2 00 ~ '~ ~ ~ " 4 3 0 0 ~
00-~
MANOMETER HEADING (PSIAI READING (PSIA) f/
' - ^ ' " - - - ~ - -
' ' ~'~ - ~ PO - - 2 6. 75 0 0 ~
- 26 ; 6 0 2 0 "~~--- - -~~ ~~' ~ h VPU-2 0.68 44.24 0 1432 PU-2 35.0260 26.6035 VPL-1 22.86 45.40 0 1497 p
PL-1 26.4130 26.5C37 VPL-2 23.94 ~~-~ ~'
47.51
~ 0 1622 -
~
~
~ ~ PL-2 -~~
~26'.5500
-'-~26.5800' ~ ~ - '-- ~
be i
91-1 11.53 22.73 0.u575 VPI-2
-0 52 22 6%
PI I 27.0470 26.56H8 h
_ 0 05F2 PI-2 26.6100 26 6079 Q-AVEHAGE VAPbd PHL550 Pts
-. _ _ - ~ Ah:1T ENT 28.6680 14T3567'~~
F g
SUMMARY
OF CORHF CTED AVE RAGE PRESSURES
[
OPPER CONT AINMENT (PSIA) 0.1434 S
LOWtk CONTAINHtHT (PSIA) 0.15b0 b
AVEkAGE UPPER PRESSURE (PSIA) 26.6027 ICE CONDENSEk (PS.I A ).._
- 0. 0_S N.____._..._._._ __.._...._.- AVEHA6E LUWER PRESSURE (PSIA) 26.5818 M GCICf~CONDFNSER~ PRESSURE ~(PSIAl~ 26.5884 m
AVfRA6f OMTAINMENT PRESSURE (PSIAI 26.5910 AVLkAGF CONIAINHENT PRESSURE (PSIG)-.12.2343 p
s rv
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Palisades La =.1 w/o/ day
.75 La
.075 w/o/d P.a 55 psig Containment Volume Pt = 28 psig Report Date Type A Type B and C May 1970 Full Pressure 0.00482 w/o/d Reported in semi-annual reports.
Preop Half Pressure 0.0223 w/o/d Preop May 1974 Half Pressure 0.0342 w/o/d i.
g+=#%
n.
1 o
J 4
t i
4 4
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. _ _....... _ _..., __. _.._.., _ _. -,,,_..