ML20136B806
| ML20136B806 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/01/1979 |
| From: | AFFILIATION NOT ASSIGNED |
| To: | |
| Shared Package | |
| ML19208A006 | List: |
| References | |
| GP-R-465, NUDOCS 7909120203 | |
| Download: ML20136B806 (220) | |
Text
_ _____ ___ ________ _ _ __________ ___________________________ _ ________
l l
OYSTER CREEK NUCLEAR GENERATING STATION INSERVICE INSPECTION PROGRAM UPDATE TO THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI 1974 EDITION THROUGH THE SUMMER 1975 ADDENDA Prepared for Jersey Central Power and Light Company I
GP-R 465 March 1,1979 I
955W21 General Physics Corporation Columbia, Maryland M
Cnaiso 2.0C3
Rev. 2 TABLE OF CONTENTS Page TABLE OF CONTENTS i
SECTION 1.
PROGRAM DESCRIPTION 1.0 Introduction.
1-1 1.1 Date of implementation.
1-1 l.2 Future Updates.
1-2 1.3 Report Outline.
1-2 l
1.4 Inservice Diagrams.
1-2 l
1.5 Summary of Systems Reviewed 1-3 l
APPENDIX 1A INDEX OF INSERVICE DIAGRAMS 1A-1 APPENDIX 1B SYSTEM DRAWING LIST 1B-1 SECTION 2.
PUMP AND VALVE TEST PROGRAM Table of Contents.
2-1 2.0 Introduction.
2-1 2.1 Pump Test Program 2-1 2.2 Valve Test Program.
2-2 APPENDIX 2A OYSTER CREEK PUMP TEST PROGRAM 2A-1 APPENDIX 2B EXPLANATION OF CODES AND SYMBOLS USED IN THE OYSTER i
I CREEK VALVE PROGRAM 2B-1 APPENDIX 2C OYSTER CREEK VALVE PROGRAM. 2C-1 APPENDIX 2D NRC STAFF GUIDANCE FOR PUMP AND VALVE PROGRAM SUBMITTALS 2D-1 SECTION 3.
WELD AND SUPPORT INSPECTION PROGRAM Table of Contents.
3-1 3.0 Introduction.
3-1 3.1 Program Update Description.
3-2 3.2 Technical Approach.
3-3 3.3 Key Technical Points.
3-4 i
4 I
o 1
e 4
TABLE OF CONTENTS (continued)
Page_
SECTION 3.
(continued) i APPENDIX 3A EXAMINATION
SUMMARY
- ASME l
CLASS 1 SYSTEMS & COMPONENTS 3A-1 APPENDIX 3A Addendum 1 -
SUMMARY
FROM 3A-10 JERSEY CENTRAL POWER AND LIGHT REPORT APPENDIX 3B EXAMINATION
SUMMARY
- ASME CLASS 2 SYSTEMS & COMPONENTS 3B-1 APPENDIX 3C PIPING WELD AND SUPPORT q
INSPECTION PROGRAM 4
Table of Contents 3C-i i
i l
l l
l l
l l
l I
I i
11
LIST OF EFFECTIVE PAGES Page No.
Revision No.
Date f
0 3fjf79 2
6/25/79 jj 0
jjj 3fjf79 1-1 3/1/79 1-2 0
3/l/79 i
j3 Appendix 1A (IA-1) fh
/
)
endix 18 (18-1-2) 2 6/25/79 3/I/78 2-1 3/1/79 2-2 2-3 3/I/78
~2 Appendix 2A (2A-1) 0 Appendix 28(28-1) 2 6/25/79 Table 28-2 l'28-2 0
3/j/79 Table 28-3I28-3)
Table 28-4 I,28-4))
0 3/1/79 0
3/i/79 Table 28-5
,28-5 0
Table 28-6I(28-6))
3/1f79 0
3fjj79 Table 28-7 I,28-7-8 0
3/j/79 Table 28-8 (28-9) )
0 3fjf79 Apendix2C(2C-1-4) 2 6/25/79 P
Appendix 2D (2D-1-12) 0 3/j/79 hi 0
3/j/79 3-1 0
3/j/79 l
3-2 0
3/1/79 3
0 3/1/79 3-4 a
0 3/1/79 I c 3-5 0
3fjj79 3-6 0
3/1/79 F7 0
3/1/79 3-8 2
6/25/79 l
3-9 2
6/25/79 l
(,_j 2
6/25/79 2
6/25/79 34j 2
6/25/79 l
2 6/25/79 l
3A-5 2
6/25/79 3A-6 2
6/25/79 3A-7 2
6/25/79 l
3A-8 2
6/25/79 111
LIST OF EFFECTIVE PAGES Page No.
Revision No.
Date 3A-9 2
6/25/79 3A-10 2
6/25/79 3A-11 2
6/25/79 3A-12 2
6/25/79 38-1 2
6/25/79 38-2 2
6/25/79 Appendix 3C (3C-1) 0 3/1/79 Table 3C-2 I(3C-1)
Table 3C-1 I 0
3/1/79
,3C-2-4) 0 3/1/79 Table 3C-3 i 3C-5-7 0
0 3/1/79 1
I t
l ll l
J'
, j? t l l.
l E j;
l<
l IV
SECTION 1.
PROGRAM DESCRIPTION - INSERVICE INSPECTION PROGRAM FOR OYSTER CREEK NUCLEAR GENERATING STATION 1.0 Introduction As amended on February 12, 1976 (and effective on March 15, 1976), Title 10 of the Code of Federal Regulations, Part 50.55a(g) requires that inservice inspection and testing be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and Addenda.
10 CFR 50.55a further requires that inservice inspection and testing shall comply with Editions and Addenda of the Code which are in effect no more than six months prior to the start of the regular 20-month inspection period.
For the Oyster Creek submittal, the effective code is the 1974 Edition through the Summer 1975 Addenda.
The program presented in this report has therefore been prepared in accordance with the 1974 Edition of the ASME Boiler l
and Pressure Vessel Code,Section XI, through the Summer 1975 Addenda, except for relief requested under the provisions of 10 CFR 50.55a (g) (5) (iii).
The data presented is consistent with the NRC letter of January 1978 entitled, "NRC Staff Guidance for Compliance with Certain P covisions of 10 CFR 50.55a(g) Inservice l
Inspection Requirements.
1.1 Date of Implementation In accordance with 10 CFR 50.55a, the program described in this report becomes effective on December 8.1979, which marks the completion of one hundred and twenty months from the start of commercial operation for the Oyster Creek Nuclear Generating Station.
1 1-1
l.2 Future Updates The test and inspection programs described in this report will be updated on April 8, 1983 (40 months from the date of implementation) to comply with the provisions of 10 CFR 50 in effect at that time.
1.3 Report Outline Section 2 of this Report contains the Pump and Valve Test Programs and Section 3 contains the Weld and Support Inspection Program.
Each of these sections is self-contained and includes the program along with the necessary codes, symbols, abbrevia-tions and supporting data to permit detailed review.
1.4 Inservice Diagrams Submitted with this Report is a set of Inservice Diagrams which show all systems and portions of systems in the Oyster Creek Plant which are ASME Class 1, 2, or 3.
Code classifica-tions were prepared using the guidance in 10 CFR 50.2(v) for ASME Class 1 and NRC Regulatory Guide 1.26 for Class 2 and 3.
The diagrams included with this report are color-coded to facilitate review of these programs.
An index of these Inservice l
Diagrams is included as Appendix 1A with this section of the Report.
As shown in this Appendix, drawing JCP-19431 contains the legend and symbols used on the ISD's.
1A Proposed Rule recently published for comment in the Federal Register would leave the Program described in this Report in effect for the full 120-month inspection interval beginning December 8, 1979.
In the event that this Proposed Rule is in-corporated in 10 CFR 50, no Program updata will be required until December 8, 1989.
l l-2 1'
l 1.5 Summary of Systems Reviewed In determining the location of ASME Code Class 1, 2 and 3 boundaries, the systems and drawings shown in Appendix 1B were reviewed.
[-
b h5
?.
ki s
i;
?,
Ll I
I
\\'I l-3
APPENDIX 1A INDEX OF INSERVICE DIAGRAMS ISD Number Title JCP-19418 Isolation Condenser System JCP-19419 Poison System JCP-19420 Containment Spray System JCP-19421 Reactor Recirculation System JCP-19422 Core Spray System JCP-19423 Main Steam System JCP-19424 Condensate Transfer System JCP-19425 Fire Protection System JCP-19426 Miscellaneous Class 1 & 2 Systems Penetrating Containment
- JCP-19427 Service & Emergency Service Water System JCP-19428 Closed Cooling Water System JCP-19429 Hydraulic Control Unit JCP-19430 Fuel Pool Cooling System JCP-19431 Symbols & Legend for ISD & Isometric Drawings l
~
- Includes:
Feedwater, Reactor Head Cooling, Demineralized Water Transfer, Clean-up Demineralizer, Shut-down Cooling, CRD Hydraulic Return, and Drywell Floor & Equipment Drain Systems t
r 1A-1 l
Pev. 2 APPENDIX IB SYSTEM DRAWING LIST System Status Dwg. Number ISD Number Isolation Condenser XI GE-148F262 JCP-19418 Reactor Shutdown Cooling XI GE-148F711 JCP-19426 Rx. Level, Press, Temp, XI GE-148F712 N/A Instr.
Poison XI GE-148F723 JCP-19419 Containment Spray XI GE-148F740 JCP-19420 Clean-Up Domineralizer XI GE-148F744 JCP-19426 Hydraulic Control Unit XI GE-197E871 JCP-19429 CRD Hydraulics XI GE-237E487 JCP-19426 Drywell & Suppression XI/(A)
GE-237E726 N/A Fuel Pool Cooling XI GE-237E756 JCP-19430 Reactor Recirculation XI GE-237E798 JCP-19421 E-CRD Hydraulics XI GE-706E249 N/A Core Spray XI GE-885D781 JCP-19422 Reactor Head Cooling XI GE-886D403 JCP-19426 Main Steam XI/(A)
BR-2002 JCP-19423 b
Feedwater & Condensate XI BR-2003 JCP-19426 lRev. 2 Cond. & Demin. Water XI BR-2004-2 JCP-19424/
Transfer JCP-19426 L
Serv. & Emer. Serv. Water XI BR-2005 JCP-19427 Rx. Bldg. Closed Cooling XI BR-2006 JCP-19428 Water Standby Gas Treatment (A)
BR-20ll N/A i
Instr. & Service Air (A)
BR-2013-4 N/A Fire Protection XI BR-2014-4 JCP-19425 Nitrogen Purge & Make-up (A)
BR-2014-4 N/A Radwaste Treatment XI BR-M-607 JCP-19426 l
Cont. Particulate Monitor (A)
CPM-0002 N/A Air Offgas (A)
BR-2008 N/A Heating & Process Steam NNS BR-2015-5 N/A NNS - Non-Nuclear System (A) - Augmented System ISD - Inservice Diagriun IB-1
APPENDIX IB SYSTEM DRAWING LIST (cont.)
System Status Dwg. Number ISD Number j
l H & V Radwaste Bldg.
NNS BR-2012 N/A HVAC - Office, Cable, NNS BR-2010-5 N/A Control HVAC - Turbine, Machine NNS BR-2009 N/A Shop Heater Drain, Vent, NNS BR-2007 N/A Relief Generator Gas Control NNS GE-865D743 N/A Shaft Sealing NNS GE-865D711 N/A 4
Steam Seal Piping NHS GE-713E802 g/A Process Radiation Monitor NNS GE-846D686 N/A Turbine Control Diagram NNS GE-233R303 N/A Stator Cooling Water NNS GE-234R166 N/A NNS - Non-Nuclear System (A) - Augmented System ISD - Inservice Diagram I
I l
d e-P 1B-2 k
SECTION 2.
PUMP AND VALVE TEST PROGRAM OYSTER CREEK NUCLEAR GENERATING STATION Section Title Page TABLE OF CONTENTS.
2-i
2.0 INTRODUCTION
2-1 2.1 Pump Test Program 2-1 f
2-2 Valve Test Program.
2-1 Figure 2-1 Summary of Pump and Valve Program Tables 2-2 Appendices 2A PUMP TEST PROGRAM 2A-1 2B VALVE TEST PROGRAM CODES AND SYMBOLS 2B-1 2C VALVE TEST PROGRAM.
2C-1 2D NRC STAFF GUIDANCE FOR PREPARING PUMP AND VALVE TESTING PROGRAM DESCRIPTIONS 2D-1 l
l l
l l
t.
2-1 M
l l
SECTION 2.
PUMP AND VALVE TEST PROGRAM FOR THE OYSTER CREEK NUCLEAR GENERATING STATION l
i l
2.0 Introduction The pump and valve test programs for the Oyster Creek Nuclear Generating Station are presented as Appendices 2A, 2B, and 2C to this section of the Report.
A summary of the contents j
i of these Appendices is included as Figure 2-1.
Both programs i
were developed with consideration given to the boundary classi-fication guidelines contained in 10 CFR 50.2(v) for Quality Group A and Regulatory Guide 1.26 for Quality Groups B and C.
(Quality Group A is the same as ASME Class 1, Group B is Class 2, and Group C is Class 3.)
These programs will be in effect for the 40-month period commencing December 8, 1979, which marks one hundred twenty months from the start of commercial operation.
Both programs are consistent with the 1978 "NRC Staff Guidance for Preparing Pump and Valve Test Program Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)," included as Appendix 2D.
2.1 Pump Test Program The pump test program shall be conducted in accordance with Subsection IWP of Section XI of the 1974 Edition of the ASME Boiler and Pressure Code through Summer 1975 Addenda, except for relief requested under the provisions of 10 CFR 50.55a(g) (5) (iii).
Table A, Appendix 2A, includes a list of pumps which require operational testing under the guidelines of Section XI, Subsec-tion IWP-1100, and specific requests for relief.
Test parameters which will be measured for each pump are indicated.
2-1 m
_ _ Ma-i
2.2 Valve Test Program The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the 1974 Edition of the ASME Boiler and Pressure Vessel Code through the Summer 1975 Addenda, except for relief requested under the provisions of 10 CFR 50.55a (g) (5) (iii).
The valve test program is incluaed as Appendix 2C.
The codes and symbols used to abbreviate the tables in Appendix 2C are explained in Appendix 2B.
Specific requests for relief are presented in Tables 3 and 3A of Appendix 2C.
Appendix Table No.
Table Title 9
2A A
Pump Test Program y
2B B-1 Valve Test Program Matrix p
2B B-2 Symbols Used to Designate " Valve Type" 2B B-3 Symbols Used to Designate " Valve Actuator 5
Type" l
r 2B B-4 Symbols Used to Designate " Valve Position" 2B B-5 Symbols Used in the " Test During" Column 2B B-6 Symbols for " Valve Test Method" 2B B-7 Generic Codes Identifying Requests for Relief I
2C 1
Valves Being Tested in Accordance with Code Requirements 2C 2
Valves for Which Seat Leakage is Important l
2C 3
Valves for Which Relief is Being Requested 2C 3A Clarification of Request for Relief Figure 2-1 Summary of Pump and Valve Program Tables i
2-2 y.
i
Rev. 2 Category A valves are those which perform a pressure isolation function.
There are no valves in the Oyster Creek plant, which, if they leaked, could result in damage to downstream components.
Leakage through containment isolation valves is evaluated under the provisions of 10CFR$0, Appendix J, Type C.
l l
t l
l l
i 2-3
APPENDIX 2A OYSTER CREEK PUMP TEST PROGRAM l
Summary of Information Provided i
The pump test table (Table A) provides the following information:
Individual pump identifier The Inservice Diagram (ISD) on which the pump is depicted ISD Coordinates III Speed Inlet Pressure (
Differential Pressure (
Flow Rate Vibration Amplitude ( }
Test Interval (1)
These parameters are each addressed with an entry consisting simply of a "yes" or "no,"
indicating whether or not the parameter will be monitored during the 40-month program.
2A-1 5
Sf87th CAtt4' NUCLEAR P6WEA STAT 103 INSERVICE ICSPECTIOb PUMP TEST PROGRAM PREPARED bYI W.J. RUDOLPH DATEI 05/19/Tb REVIEWED BYI N.
HOLLAND DATE: 0S/23/78 APPROVED BY CHIEF ENGINEERI H. ASRWITh DATLI 10/04/78 eeeeeeeeeeeeeeeeee.............ee.
..ee.....eeeeee....eeeeeee..
...........e...e............e.....................................
e TEST PARAMETERS e
e e
e e
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.....................
e SYSTEM e
ISL e
PUMP e
PUMP e C00R0e a e
e e
TEST
=
e
- AUMEER *
= NUM6ER e
e SPEED e INLET e DIFFERENTIAL. FLOW = VIERATION. I N TE R V AL e
e (23 e PRESSURE e PRESSURE
. RATE.
AMPLITUDE e
(3) e e
e e
e (6) e (6) e (1) e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee........e eeeee.........eeeeeee POIS03 19419 "A" POIS0N PbMP NP-02A E-S NO YEst4)
YES YES N0t 73 92 D AYS POIS03 19419 "B"
POISON PUMP NP-02E H-5 NO YESt43 YES YES A0t71 92 D AYS CO2C SPRAY 19422 "A"
CORE SPhAY h201-A G-N NO YES YES YEstS)
YES 92 DAYS CORE SPRAY 19422 "B"
CORE SPRAY NZB1-8 G-11 NO YES YES YEStS)
YES 92 DAYS CCCC SPRAY 19e22 "C"
CORE SPRAY N201-C G-Y NO YES YES Y[$tS)
YES 92 D AYS CORE SPRAY 19422 "D"
CORE SPRAY NZO1-0 Ga1G NO YES YES YEstS)
YES 92 DAYS CORE SPRAY 19422 "A"
BOOSTER PUMP NZO3-A D-8 NO YES YES YEstS)
YES 92 DAYS CORE SPRAY 19422 "8"
B00 STER PUMP NZO3-8 D-11 NO YES YES YES(5)
YES 92 DAYS CO2C SPRAY 19422 "C"
BOOSTER PUMP NZO3-C 0-10 No YES YES YEft5)
Yrs 92 DAYS CORE SPRAY 19422 "0" 600 STER PUMP NZO3-D D-10 40 YES YES YEstS)
YES 92 DAYS eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee...............................................e..................
F00T40TESI (13 VIBR ATION 'IS A SINGLLARLY RELIABLE INDICATION OF PUMP MECHANICAL CONDITIONI THUS BEARING TEMPERATURE PEA (2) SYNCHRONOUS OR INDUCTION MOTORS 00 NOT REQUIRE A SPEEC CHECK (IWP-4400).
(3)
PUMPS WILL EE TESTED PER IWP EVERY 92 DAYS.
THE IN LIEU OF TESTING EVERY 31 DAYS WILL CONSIST OF ROLLING TME PUPP TO LUBRICATE THE BEARIhGS AND MEASURING ONLY ONE (1) PARAMETER.
443 INITIAL AND OPERATING INLET PRESSURE DETERMINED BY WATER LEVEL.
85)
CORE SPRAY %AIN AND BOOSTER PUMPS WILL BE TESTED SIpuLTANEOUSLY AND TOTAL FLOW WILL PE RECORCED.
(6)
IN A FINED RESISTANCE SYSTEM IT IS REGUIRED TO MEASURE DIFF. PRESSURE OR FLOW RATEe NOT BOTH. SEE TABLE IWP-31G0-1 (1974 E CEE )
(7) VIBRATION MLASUREMENTS FR0 VIDE NO MEAN!h6FUL DATA ON A POSITIVE DISPLACEMENT PUMP.
PAGE 1 g
c ns
~ m: m :w~
s
- ~
- w
'SYSTER.C.TEER CUCLEAR POWER' STATION.
INSERVICE ItSPECTION PUMP TEST PROGRAM FREPARED oY: n.J. RUDOLPn CATE: 05/19/T8 REVIEWED BY: N. HOLLANC DATE: 0S/23/18 APPROVED BY CHIEF ENGINEERI H. ASMWITH DATE: 10/04/78
.....................e...................-s..............................e..........................................
TEST PARAMETERS
...................e..................................
SYSTEM e
ISC PUMP PUMP
. COORD..
. htMBER *
- NUMBER *
. SPEED. INLET TE S T DIFFERENTIAL. FLOW VIPRATION. INTERVAL (2)
. PRES $URE.
PRESSURE
. RATE. AMPLITUDE.
(33
...e.e.......................................................e........................e................e...........(.1)
(El
. (6)
CO3TAIN. SPRAY 19420 1-1 CONT. SPRAY S1-A G-6 NO YEst43 YES YE5 YES 92 DAYS C03TAIN. SPRAY 19420 1-2 CONT. SPRAY bi-8 M*6 10 YEst4)
YES TES TES 92 DAYS CCMTAIN. SPA 4Y 19420 1-3 CONT. SPRAY 51-C G-9 N0 YEst43 YES YES YES 92 DAYS i
CONTAIN. SPRAY 19420 1-4 CONT. SPRAY 51-D M-9 NO YESt4)
YES YES YES 92 DAYS SERVICE WATER 19427 1-1 SERV WTR PUMP 1-1 h-1 NO YES(43 YES YE5 YES 92 DAYS SERVICE WATER 194CT 1-2 SERV WTR PUMP 1-2 h-3 NO YES843 YES YES YES 92 DAYS ECER SERV WATER 19427
.A. EMER. PUMP 1-1 H-9 NO YESi4)
YES YES YES 92 DAYS l
ECER SERV WATER 19427
- 8. EMER. PUMP 1-2 H-8 NO YEst4)
YES YES YES 92 D AYS EMER SERV WATER 19427
.C. EMER. PUMP 1-3 H-7 NO YESt4)
YES YL5 YE5 92 DAYE EKER SERV WATER 19427
.D. EMER. PUMP I-4 H-6 NO YESi4)
YES YES YES 92 DAYS F00ft0TES:
(1)
VIBRATION IS A SIhGLLARLY RELIABLE INDICATION OF PUMP MECHAh! CAL CONDITIONI THUS BEARING TEMPERATURE 423 SYNCNRONOUS OR IkOUCTION MOTORS CD NOT REQUIRE A SPEED CHECK (IWP-44003.
(3) PUMPS WILL EE TESTED PER IWP EVERY 92 DAYS.
ThE IN LIEU OF TESTING EVERY 31 DAYS WILL CONSIST OF ROLL ING Te! PUNP 10 L LB hl C A TI THE BEARINGS ANG MEASURING ONLY CAE (1) PARAMETER.
(4)
INITIAL AND OPERATING INLET PRESSURE DETERMINED bY WATER LEVEL.
459 CORE SPRAY MAIN AND E00hTER PUMPS ulLL SE TESTED SIMULTANCOUSLY AND TOTAL FLOW WILL BE RECORCEO.
(6) 14 A FIXED RESISTANCE SYSTEM IT IS REQUIRED TO MEASURE DIFF. PRESSURE OR FLOW RATEe NOT POTH.
SEE TABLE IWP-3100-1 (1974 COCE) 47)
VIBRATION MEASUREMENTS PROVIDE N0 MEANINGFUL DATA 04 A POSITIVE DISPLACEMENT PUMP.
PAGE 2 v.
r,
==.m.e w
- STSTER[ CREED NUCL'EAA POWER STATION io
' INSERVICE INSPECTION PUMP TEST PROGRAM
!'PACPARED BYI W.J. RUCOLPe DATES Cht19 tit REVIEWED eVI N. HOLLAnC DATEI 05/23/78
(
APPROVED BY CHIEF ENGINEERI H.
ASNWITH DATEI 10/04/Ts
{.....................................................................................................................................
TEST PARAMETERS SYSTEM e
ISD PUMP PUMP
. C00RD..
TEST
. hbMBIR *
. NU46ER
. SPEED. INLET DIFFERENTIAL
. FL0h
- VIPhATION INTERVAL e
. (2). PRESSURE.
PRESSURE RATE AMPLITUDE *
(33 e
e (6)
. (6)
(1)
.....s...........e........................s......................
....e..............................................................
FIRE PROTECTION 19425
.A. DIESEL PUMP 1-1 F-2 YES YES(4)
YES YES TES 92 DAYS I
I l
FIRE PROTECTION 19425
- 8. CIESEL PUMP 1-2 C-2 YES YES(4)
YES YES YES 92 D AYS C0%DECSATE TRANS. 19424
.A.
COND. PUMP 1-1 F-7 40 YES(4)
YES YES YES 92 DAYS f
CONOENSATE TRANS. 19424
- 8. COND. PUMP 1=2 H-7 40 YESt4)
YES
?ES TES 92 D AYS l
CLOSE3 COOL WTR 19424 1-1 CCW PUMP 1-1 E-6 NO YES YES YES YES 92 DAYS I
CLOSED C00L WTR 19428 1-2 CCW PUMP 1-2 F-6 40 YES VES YES YES 92 D AYS FUCL POOL COOLING 19430
.A.
FPC PUMP NN01A 6-7 NO YES YES YE!
YES 12 DAYS FUEL POOL COOLING 19430
.B. FPC PUMP NN018 J-7 40 YES YES YES YES 92 DAYS 1
i F6STECTESS (1) (IBRATION IS A SIhGUL ARLY RELI ABLE INDICATION OF PUMP MECHANICAL CONDITIONS THUS BE ARING TEMPER ATURE ME ASUREFENT (2)
SYNCHRONOUS OR IhDUCTION MOTORS 00 NOT REQUIRE A SPEED CHECM IIWP-44 Col.
(3) PUMPS WILL BE TESTED PER IWP EVERY 92 DAYS.
THE IN LIEU OF TESTING EVERY 31 DAYS WILL CONSIST OF ROLLING TMF PUMP T O L UB R I C A T E THE BEARINGS ANC MEASURING ONLY ONE (1) PARAMETER.
(4)
INITIAL AND OPERATIhG INLET *RESSURE DETERMIhED BY WATER LEVEL.
(S)
CORE SPRAY PAIN AhD BOOSTER FUMPS WILL BE TESTED SIMULTANEOUSLY AND TOTAL FLOW WILL EE RECORP D.
t (6)
IN A FINED RESISTANCE SYSTEM IT IS REQUIRED TO MEASURE DIFF. PRESSURE OR FLOW RATE. NOT bOTH.
SEE TABLE IbP-3100-1 (1974 COEE)
(T)
VI6 RATION MEASUREMENTS PP9VICE NO MEAh!NGFUL DATA ON A POSITIVE DISPLACEMENT PUMP.
PAGE 3
!/S.,
Fev. 2 APPENDIX 2B EXPLANATION OF CODES AND SYMBOLS USED IN THE OYSTER CREEK VALVE PROGRAM l
l Purpose The tables included in this Appendix identify the codes and symbols used in the valve test program presented in Appendix 2C.
These tabics can be removed from the report to assist in reviewing and understanding the information provided in the valve program.
Tables In accordance with standard General Physics practice, the Valve Test Program included in this Report is divided, by system, into the following tables:
4 Table 2B-1.
List of Tables Table No.
Contents 1
Valves tested in accordance with Code requirements.
2 Category A valve leak rate values.*
lRev. 2 I
3 Valves for which relief from Code requirements is requested.
(
3A Clarification of requests for relief included in Table 3.
l
- See P. 2-3 for statement concerning Category A valves at Oyster Creek plant. (Rev.2 2B-1 fi
~.
z
~ -
2 -
i
Table 28-2 Valve Test Program Matrix NUMBER OF PAGES REV.
Table Table Table SYSTEM ISD NUMBER NO.
1 3
3a Isolation Condenser JCP-19418 0
1 Reactor Shutdown Cooling JCP-19426 0
1 1
Poison JCP-19419 0
2 1
1 Containment Spray JCP-19420 0
2 Clean-Up Demineralizer JCP-19426 0
1 1
1 Hydraulic Control Unit JCP-19429 0
1 1
1 CRD Hydraulic JCP-19426 0
1 1
1 l
Fuel Pool Cooling JCP-19430 0
1 Core Spray JCP-19422 0
4 1
1 Reactor Head Cooling JCP-19426 0
1 Main Steam JCP-19423 0
2 1
1 Feedwater JCP-19426 0
1 1
1
~
Condensate Transfer JCP-19424 0
2 i
(
i t
I Serv. & Deer. Serv. Water JCP-19427 0
1 1
1 Rx. Bldg. Closed Cooling Wtr.
JCP-19428 0
1 1
1 Fire Protection JCP-19425 0
2 Radwaste Treatment JCP-19426 0
1 l
l I
Demin. Water Transfer JCP-19426 0
1
'l
!l NOTE: Table 2 is not required in the Oyster Creek Valve Test Program
[
2B-2 I
1 i
l Table 2B-3 Symbols Used to Designate Valve Type l
VALVE TYPES Symbol Meaning AN Angle Valve BF Butterfly BL Ball CK Check f.
DA Diaphragm GA Gate GL Globe i
PG Plug RD Rupture Disk l
RG Regulating RL Relief SC Stop Check a
SK Spring Check I
3
'1 1
l y
t s
2B-3 a:
Table 2B-4 Symools Used to Designate V21ve Actuator Type VALVE ACTUATOR TYPES Symbol Meaning A
Air Operator M
Manual Operator Mo Motor Operator SA Self Actuated A'
S Solenoid Operator 4
H Hydraulic Operator E
Electrical XP Explosive Operator
'k 3
I-I
Table 2B-5 Symbols Used to Designate Valve Position VALVE POSITIONS Symbol Meaning O
Open C
Closed ID Locked Open l
If Incked Closed TH Throttled Valve position determined by other system parameters l
as in the case of any 2B-5
k Table 2B-6 Symbols Used in the Test During Column l
The Codes used in this column indicate the plant operational status that must be achieved before a particular valve can ce safely tested. For simplicity only the three following codes are used:
l Test During Plant Operational Status 3
Normal Operation. Valves in this category may be tested during normal operation without any adverse effects on operations or safety.
2 Cold Shutdown. Testing of valves in this category must be deferred until cold shutdown in order to avoid pos-sible adverse operational or safety situations.
l l
^
1 Refueling. Testing of valves in this l
category must be deferred until the l
plant is in a refueling mode in order to avoid possible adverse operational or safety situations. For Category E
~
valves and passive valves, this symbol indicates that log entries i
and/or operational checks are made as required during all plant conditions.
l l
2B-6 w
Table 2B-7 Symbols for Valve Test Method CATEGORY A OR B VALVES EF-1 Exercise valve (full stroke) for operability every 3 months in accordance with Section XI, Article IWV-3410.
EF-2 Exercise valve (full stroke) for operability during cold shutdown mode only.
EF-3 Exercise valve (full stroke) for operability during refueling mode only.
EF-4 Exercise valve (with remote position indicator and inaccessible for direct observation) for verification of valve position during refueling, but less than every 2 years in accordance with Section XI, Article IWV-3300.
EF-5 Exercise valve (with fail-safe actuators) to observe proper
@eration of fail-safe mechanisms every 3 months in accordance with Section XI, Article IWV-3410.
EF-6 Exercise valve (with fail-safe actuators) to observe proper operation of fail-safe mechanisms during cold shutdown.
EF-7 Exercise valve (with fail-safe actuators) to observe proper 4
operation of fail-safe mechanisms during refueling.
ET-1 Exercise valve to measure the full stroke time of a power operated valve. 'Ihe valve stroke will conform to the require-ments specified in Technical Specifications.
ET-2 Exercise valve to measure the full stroke time of a power operated valve. The valve stroke test will be performed in accordance with IWV-3410.
SLT-1 Seat Leak Test Valve during refueling, but less than every 2 years. Leak rate limits will be established after initial baseline testing in a manner to be specified by the licensee.
PV-1 Operational checks with appropriate record entries shall record the position of these passive valves before operations are performed and after operations are completed.
NOTE:
Passive valves are valves that are not required to change position to accomplish an essential function.
r r
i 2B-7
Table 2B-7 (Continued)
Symbols for Valve Test Method CATEGORY C VALVES EF-1 Exercise valve (full stroke) for operability every 3 months in accordance with Section XI, Article IWV-3500.
EF-2 Exercise valve (full stroke) for operability during cold shut-down mode only, with a frequency not to exceed once every 3 mos.
EF-3 Exercise valve (full stroke) for operability during refueling mode only.
l TF-1 Testing of safety and relief valve set points in accordance with IW-3510.
NOTE:
On Category C check valves, whose function is to prevent reverse j
flow, the test will be performed to prove that the disk travels l
~
to the seat promptly on cessation or reversal of flow.
h l
CATEGORY D VALVES RD-1 Operational checks of rupture discs shall be performed in accordance with the manufacturers recomunendations. The fre-quency of those tests shall be specified by the Owner in accordance with IW-3620.
l XP I Operational checks of explosive charges will be performed during each refueling outages or at a frequency not to ex-j ceed 2 years in accordance with IWV-3610.
l i
CATEGORY E VALVES OC-1 Operational check of valve to verify that the valve is either l
locked open or locked closed before and af ter operation in accordance with Section XI, Article IWV-3700.
l I
-I
4 Table 2B-8 Generic Codes Identifying Code Exemptions and Requests for Relief E-1 The exercising of valves whose failure in a nonconservative position during the cycling test would cause a loss of system function.
E-2 The exercising of valves whose failure to close during a cycling test would result in a loss of containment integrity.
E-3 tite exercising of valves which could subject a system to pressure in excess of its design pressures.
E-4 Valves which cannot be seat leak tested.
t E-5 valves which cannot be exercised (verification of full stroke)
I due to their design, physical location, arrangement, alignment or orientation in the system.
E-6 Valves whose access may be restricted due to a high radiation area coupled with its physical location and arrangement in the system.
E-7 valves (pressure regulating, flow control, throttling, etc.)
l used for operating convenience or system control.
h l
l l
l
~
2B-9 x-s i-w
Rev. 2 APPENDIX 2C OYSTER CREEK VALVE PROGRAM Summary of Information Provided j
i i
Table 1, " Valves Being Tested in Accordance with Code Require-ments," identifies all of those valves which will be tested in accor-Rev.
dance with the provisions of Section XI of the ASME Boiler and Pres-sure vessel Code.
The following information is provided on Table 1:
System Name Inservice Diagram (ISD) Number e
e Valve Number Quality Group Classification Coordinate Location of Valve on ISD Valve Category per Section XI, IWV-2110 Valve Size Valve Type Actuator Type e
Normal Position Test During Column.
This column identifies the plant l
operating status required in order to test the 1
valve without compromising safety.
Test Method Column.
This column identifies the Section XI Code inspections that will be performed I
on each valve.
Remarks as necessary Codes and symbols used on this table are identified in Appendix 2B.
Table 3,
" Valves for Which Relief is Being Requested,"
identifies those valves for which the Code requirements for inspection are impractical and a request for relief is being 2C-1
made, as provided in 10 CFR 50.55a (g) (5) (iii).
The following information is being provided on Table 3:
System Name ISD Number Valve Number Quality Group Classification Coordinate Location of Valve on ISD Valve Category per Section XI, IWV-2110 Valve Size Valve Type e
Actuator Type Normal Position Test During Column.
This column identifies the plant operating status required in order to test the valve without compromising safety.
Test Method Column.
This column identifies the Section XI Code inspections that have been determined to be impractical for the valve.
Reason for Requesting Relief.
Two entries may be pro-vided in this column.
The first entry represents a generic reason and is presented in the form of a code prefixed by the letter E.
The second entry refers the reader to amplifying notes contained on Table 3A which serve to further clarify the request for relief.
Testing to be Performed.
This column is used to specify the in lieu of testing which will be performed as a substitute for the testing specified in Section XI of the Code.
I Table 3A, " Clarification of Request for Relief," provides l
further justification, if needed, to support any request for relief from Code inspection (s) :
System Name 2C-2 s
ISD Number Note Number Valve Number Remarks for Justification of Request for Relief I
s i
4 A
/
w s
1 1
,b s
1.
3--
l 2C-3 c
'a
.at
?
Oyster Creek Valve Program Tables Table 1 - Valves Being Tested in Accordance with Code Requirements Table 2 - Valves for which Relief is being Requested Table 3 - clarification of Request for Relief i
i i
t d
i r
2C-4 L
- u-
,2
?,
_ _ - - _ - _ - - - - - - - ~ - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
y,-
.7 n
~,,
g.
l a
~
~
'TA9 e
eeeeeeeeessseeeee oo. eeeeee....LE 18 UALVES SE
..... eeeeeeece.ING TE.STE.S IN ACCORGANCE WITH COGE REQUIREMENTS.......
2e...86/18#T 9 R
..ee.......eeeeeeeee e
.eeeeee..
e SYSTENs ISOLATION CON 0ENSE*
ISD NO.8 K P-19418 OTSTER CREEK, UNIT 1 o
e e ocepAeED 9V8 H. LL0v0 OATEI Ot./28/78 e
l e
REVIEWE0 ST8 N. HOLLANO" DATES 86/OF#F S f
soooooo o o oo s e.o o s e e o o e e e ee e e e e e e e ee e ee e e e e s s s e s s e e ee e ee e ees s s e e
o VALVE e VALVE NU1Rr*
e CLAS$ C0090 CATEGORY SI7F WALVE ACT.
Netn.
TEST TEST e
e IN ATE A8CDE 01 TVPE
'YPE POS.
OURING METHO D
- R E M A R st S eeee eee e e ee s se e. e e - ee e e e e ee e e e e e e e ee.o o o o o o o o o e s e e%
eeeeeeeesoseesses sesses eeesse oo esses see ooe.cocoeseeee eeeeesseeee s
V14-30 1
8-8 x
16 CA NO O
3 EF-1 3
ET-1 i
914-11 1
8-8 y
16 GA MO O
3 EF-1 4
3 ET-1 W14 32 1
A-4 Y
16 CA MO O
3 EF-1 3
ET-1 h
.v14-33 1
A-4 N
16 GA NO O
3 EF-1 3
27-1 T14 36 i
F-12 X
13 CA no 0
3 EF-1 3
ET-1 1
EF-4 v14-17 1
F-11 Y
13 GA NO O
3 EF-1 i
3 ET-1 1
EF=,
V 14-35 1
C-10 x
11 GA MC C
3 EF-1 L
t 3
ET-1 W14-34 i
C-13 X
10 GA MC C
3 EF-1 3
ET-1 vib-4 2
C-6 8.79 GL n
a 1
av 1 v14-2 2
C-5 Y
8.'9 GL M
0 1
PV-1 l
vi b-1 2
C-5 O.74 GA A
0 3
EF-1 3
FF-5 3
ET-2 V1%=9 2
C-6 W
S.75 Ga A
0 3
EF-1 3
EF-5 3
ET-2 i
A**80vr9 H.M.
A!<WITH. Cwger
?NGIMEf8 QATEt 10/ P4 / To PAGE 1
Mr ma ~
M-i 1,
A.
2 m
(
s e.
...................................FABL.E...St... val VE S.FOR..W.N T C.M RE.L IE.F.......
..I.S SE.ffeG REQUE.S.TE.D.......................
2,... 86/18/79
- EW.
e
- tv5FEw8 efACTOR $54UT00W4 000LIPtG e
ISO 800.8 JCP-19426 OYSTER CREEK, UNIT 1
REVIEWE0 SYS N DATE: 86t D6tr e
............................................................................................... HOLLAND VALVE
- VALVE NU19E 8
- CLASS C0040 CATEC04Y SIZF VALVE ACT.
N0* N.
TEST TEST REQUESTING TO SE REASON FOR T EST! teG
- e o................................INATE.eeee.A81 C 0 F...............I.... TYPE.... TYPE...PO.S....... RING.................ENEMPTICN.
(!N DU 8eETM00 P
V17-5 6 1
'-T x
14 GA NO C
EF-1 E-5 NOTE 1 EF 2 ET-1 E-5 E T-1 l
1 EF=4 V17-55 1
0-12 X
4 GL NO C
EF-1 E-2 NOTE 2 EF-2 ET-1 E-2 ET-1 V17-4 6 1
n-11 x
8 GL NO C
EF-1 E-2 NOTE 2 EF-2 ET-1 E-2 ET-1 V1747 1
0-10 W
9 GL NO C
EF-1 E-2 NOTE 2 EF-2 ET-1 E-2 ET-1 V17-19 1
F-4 X
14 GA NO C
EF-1 E-5 NOTE 1 EF-2 ET-1 E-5 ET-1 1
EF-4 I
V17-1 1
3-14 4
10 GA NO C
U-1 E-2 NOTE 2 EF 2 ET-1 E-2 ET-1 1
Vi r-2 1
o-ts x
is GA NO C
u-1 E-2 NOTE 2 Er-2 ET-1 E-2 ET-1 l
V 1 F-1 1
0-12 X
10 GA NO C
EF-1 E-2 NOTE 2 EF-2 ET-1 E-2 ET-1 l
l l
I 1
l l
l 1
l l
$Ir0rfrE"Nire"*NeSiSU 1
PAGE 2
l
- ~.,- -,
+
t
~-
~
e.
+
e.--
t, l
eeeeeee e e ee ese e s.......s os on e e ee....
.....T A9L..E 34 8.....
CL. AR1 FICA T10N OF REQUEST FOR RELIEF REV 2.
06/14#7 9
......e oeee eeee ee eeeee eeee eeeee eeee e eeeee eee eee e e ee eee e ee ee.
e eeeeeeeeeoeoeseee
- SYSTE4s 8tEACTOR SHUTOOWN COOLING e
[
e ISD NO.8 JC P-19426 OVSTER CREEK, UNIT 1 l
- Por84REO RYt H.
LLOTO DATE: 05/01/78 e
l e
4EVIEWE0 SYs N. N0LLANG DATE8 86 seeeeeee e e e eee s o se eee e os se see ee e o eoo oes e ess ee oe seeee s se s eeeeeee s s se ee e
e o
e eeeeeeeee, NOTE WALvf NifMSF#
4ENAR4S o
e e
e sooesesse ssessee ee eeeeeessee ssee eeeeeees seeeeee eeseeseesseees oeseeeeeeoooose e
1 V1F=56 THIS WAL VE IS INTEELOCKES AMG CANNOT SE OPEleEO WHEN RE ACTOR PRESSURE IS A80WE W17-19 125 MIG.
'l 2
W17 55 THIS VALVE IS INTERLOCKE0 ANO C&hh0T SE OPEleEO WNEN REACTOR TEMPER ATURE IS W1 F=56 GR E A tee TN AN 39 9 Of GREES F e l
V17-5 7 V17 1
'#1 F= 2 V17 1 i
t i
(
APPe0VED8 p.d.
A sx WIT H. CHI e ENGINEER DAfra 10/24/79 PAGE 3
., m 4. -
- s/ a.,4..
..qumni n, c,,.,,.., 7 3, s -s
Gy
- "~-
rl
~~
jy % 4
- t. m 3
TAiLE 18 VALVES 9EthG TESTED IN ACCORGANCE WITH CODE REQuttEnENTS REV opeesseee ee ese s s e...........ee ee eeeeeeeooese eeeeeeeeeee eeee e eseesse eeee eeee eeeeeeeee eeeee eee ee ooesseeeeeeeeeeeeeeee. 2.
06/18#79 eee e ee e e ee ee eeee e e
o SYST'"8
- 0!90N ISO NO.s JCP-1941ip OYSTER CREEK. UNIT 1 e
e o pcEpseE0 Svt M.
LLOYO DATTI 04/2F/74 REVIEWE0 SV8 N. NOLLAN0 DATE8 86/06/Te o
e o
eeeeeee ee ee eee e e ee eee eee.ooes.. eeeeee eeeeeeeo ee eeeeeeeeeeeeee e eeeeeeeeeeeeeeeeee ee....eeeeeeee....ooeeeeeeeeeeeeee eeee eeeeeeee.
-o e
VALVg o
e
- VALVE NUM9Es
- l' LASS COORO CATE3ORY SIT' VALVE ACT.
NORM.
TEST TEST
- EMARKS e
INATF A 9C0F IIN) TYPE TVPE POS DURING METHOD
- eeeeee........s e e e e e e ee...e e e ee e o s........ eee e e eeee ee ee eee e ee e eeeeeee.
eeeeeeeeeeeeeeeee***eeeeeeee...eeeeeeeeeeeeeeeeeeeeeeeeeeeee.
V19-19 1
H-1 X
1.5 GA M
LO 1
OC-1 1
EF-4 V10-25 2
E-1 N 18 GA M
LO 1
OC-1 vi9-44 2
0-2 3
1.5 PG XP C
XP-1 THIS EMPLOSIWE VALVE WILL BE TESTED WITH
=
SYSTEM FUNCTIONAL TEST EACH REFUELING.
V19-45 2
F-2 x
15
- G XP C
WP-1 THIS EXPLOSIVE VALWE WILL BE TESTED w!TH SYSTEM FUNCT10hAL TEST EACH REFUELING.
d 19-F 5 2
C-1 K 8.75 GL M
LC 1
OC-1
- 19-7 2
E-4 Y
1.5 GA N
LO 1
OC-1 vi%e 2
H-4 X 19 GA N
LO 1
OC-1 V 19
't ?
2 F-4 W
EF-1 TEST THIS VALVE IN CONJUNCTION WITH "A "
POISON PUMP TEST.
V19-34 2
H-4 5
EF-1 TEST THIS VALVE IN CONJUNGTION WITH "S "
POISON PUMP TEST.
V 14-4 7
?
0-9 W
i RL SA C
1 TF-1 V 19-41 2
J-4 X
1 RL SA C
1 TF-1 Viv-*
2 F-F v
2.9 GA M
LO 1
OC-1 V 14-6
?
W-7 7.4 CA N
LO 1
OC-1 V 19-9 2
E-S X
2.s CL M
LC 1
OC-1 A**#0Vr 0 8 H. 't. ASTWITH, CHII" E NGINEr
- 04fft 11/Pk/F9 PAGE 4
g,
,n).
, + w :~.+ A ru-W +* M M n'-
. v :g.
r-, 4
,.g TA4LE il e
sos....e ze e e e ee ee eee ee e ee e ee ee ee e e ee eV AL.V FS REI4G TESTED IN A CCOR GA NC E.W..I T
.. eeeeeeeeeeeeeeeeee............
.................... RE v. Z..e. 8 6/18 / 7 9 e
- Sv5TEMt *0fSON e
e ISO 40.8 JCP-19419 OVSTER CREEKe UNIT 1
- PCE*A*EO SYB
- k. LLOYD DATE8 8 /2F/F%
e e
eeeeee...............ee..........................................
....e......
ee,REVIEWE0 SYS N. HOLLANO 04 tea e6/96/F8 VALVE
......eeeeeeeeeeeeeeee,o,o,.............
- VALVE MU9AF#
- CLAS1 C0010 C&TEGORY ST7! v&LVE ACT.
N0eM.
TEST TEST o
e eeeeeeeeeeeeeeeeeee...........INATF.....eeeeeeeeeeeeeeseese,seoso. TYPEPOS.
OURING METHO D
- A 9CDE (141 TV*E REM ARKS
. oeosoooesee, eeeeeeeeeeeeeeesse.cososeesesee.....eeeeeeeeeeeeeee...*
V19-11 2
F=9 X
2.5 GA 4
LC 1
OC-1 W19-4 2
G-10 Y
2.5 GA N
LO 1
OC-1 W19-35 2
J-5 Y
1 GA N
O 1
Pv.1 e
V19-1 2
F-12 4 i GL si LC 1
OC-1 91 9-16 2
0-5 t
1 GA M
0 1
P V-1 v19=2 2
F-12 x 1 GL M
LC 1
OCet i
i i
1 l
t l
i l
'.. A*P80VF Q t H.H.
ASKWITH, CH{?F ENGINEED DATFS 10/ 2./ F 9 PAGE 5
l
m.-
h TAG VALVES FOR NNI oeeeeeee e eeeee.o o eee eeee.....s e oso seeeee e.LE.3 s..eeee eee eeessee.CH RELIEF IS.BEING.RE.Q.UE.S.TE.D..................
4 REW.
...........e
- SetT !MI 80T90N e
ISO NO.8 JCP-19419 OYSTER CREEM, UNIT 1
'
- PCEPA*EO 9Y H. LLOYO DATEt 04/2T/7A e
REWIEwtD SY8 N. HOLLANO DATE8 06/06/78 l
- eoeeeee e e ee e s s e s o s e e e ee e eeee e e e e e ee e e e e e e e e e e e e e e e ee e ee ee eee e o
l VALVE
- e UALVE NUW e
- CLASS C00*D CATEG0tf SITE VALVE ACT.
N04 N.
TEST TEST REQUESTING TO SE REASON F04 T ESTI NG
- e......e..........
..............INATE...A...C. 0 Eeeeeee!NIeee sseeeeeeeeeeeeeee.. 05.ee eee e SUR.ING METH00 ENEMPTION PE RF OR fE 0
- 9 t
TV*E TYPE P
. eoe
.....oosseeeeeeeeeeeeeeeeeeeee ooseeeeeeeeo.
i V19-20 1
G-1 x
1.5 CE
$A EF-1 E-5 NOTE 1 EF-3 4
{
W19-15 1
F-1 x
1.5 CK SA EF-1 E-5 NOTE 1 EF-3 4
i e
i i
'l J
i l
1
+
I f
APPPOw 0:
H.H.
A sit w I' H, C4TPF ENCT90fE' OAYF8 1C/74/74
- AGE 6
I e........................... o.....e.T4R.E.548.....L ARIFIC4 TION OF REQU.E.ST FOR REL.IEF...
....................REW. 2.ee..... 06/1.8/F9 C
........e e
- STSYrM8 801504 3
e e
ISD NO.8 JCP=194 A9 OYSTER CNEEKo UNIT 1 e **EPap!D 9Y8 H. LLOYO DATE8 Se/27/78 1
e e
seeeeeee e se sse n e c o oe sseee o s e ee e s see ee e eee eee ee ee e eee........
......................REVIENEO bye M. NOLLANG DATE8 06/86/Fa e
e
............................................e NOTE WALVE NU19ED 7 e e
RE44RKS e eeeeeeeeeeeeeeeeeeeeee...ooeee........
...................................................................e......................
i 1
V19-?O V19-16 THIS VALVE CAN 088LY St TESTED IN CONJUNCTION NITH ACTUATFD VAL 9ES OUR[NG REFUELING SV P40CEOutt.612.4.tS2. TEST FIRING OF ErPL 4
i J
1
)
i 5
i 4
i l
app *0W Cs H.M.
aSirWITH, CHI *F k
ENGINEE9 OSTEs 11/F6/78 I
paGE F
y t
s s
TA9LE is v4LVES 9f f uG TESTED IN ACCOR0ANCE WITN CODE REQUIREnENTS oseeeeee e ee e...e ee eee ee ee e e e e eee e eeee e s seee ee ee eeeeeeeee eeee eeeeeee REW 2.
86/10/ F 9 e
.oeseeeeeeeeeoeoo o SYSTE88 8 CON T A T NME NT SPR A Y e
e
!$0 40e8 JC P-19420 OYSTEA CREEE. UNIT 1
- FoEPA*F0 Svt H.
LLOYO GATEt 84/26/F4 e
e REVIEWED SY8 N DATES 86/8F/F S eseeeeeee ee eee e e eee ee eeeeeeeeeo o osee eeess e s seee ee ess essesse.oooo ooseeeeeeee ee
...e eeee...
. e oe....
MOLL ANO e
o VALVE
- VALVE NuflTR
- CLASS COORD CATEGO*Y S!FE WALVE ACT. He0RMe TEST TEST o
e e,eee........ee.ooes........TNaTFee........CD E................E.... T V P E... PO S.
RENAR45 e
A9 t tWB TYP DutthG M
............E THO O...............................................*
l V21-10 2
F-5 X
EF-1 F04WA40 FLOW TEST WITH PUMP SLA. REVERSE FLOW TEST WITM PUw 518.
W21-4 2
H-5 4
EF-1 FORWARD FLOW TEST WITH P'JNP 518. REVERSE FLOW TEST WITM PUNP 51A.
v21-2 2
F-13 4
13 CE 1A 3
EF-1 FORWA40 FLOW TEST WITH PUMP 51C REWERSE FLOW TEST WITN PU9P 510.
V21-4 2
M-13 13 CK SA 3
EF-1 FORWARO FLOW TEST WITH PUMP 510. REVERSE FLOW TEST WITH PUNP 51C.
v21-*
2 G-18 W 14 GA N
LC 1
OC-1 I
v21-1T 2
8-6 Y
6 GA 40 C
3 EF-1 l
1 l
3 ET-2 V21-18 2
C-6 x
4 CA M
C 3
EF-1 3
ET-2 v?1 20 2
C-5 x
1 CK SA 3
EF-1 TEST THIS WALVE IN CONJUNCTION WITH PUMP A OR S TEST.
W23-11 2
8-?
Y 14 GA MO O
3 EF-1 3
ET-2 V21-13 2
C-9 w
6 GA 40 C
3 EF-1 3
ET-2 V21-15 2
C-9 F
4 CA M0 C
3 EF-1 I
3 ET-2 W21-19 2
C-10 t
1 C4 SA 3
EF-1 TEST THIS WALWE IN CONJUNCTION WITH PU4P C 0* O TEST.
921-9 2
6-9 x
in GA 40 0
3 EF-1 i
3 ET-2
\\
A***Cdfit H.H.
A$ostfM, CHI:F ENGINEFo DATE:
10/ 24/F 4 PAGE a
a
TA v6
.............see..BLE 1.s... L.VES RET NG TESTE.D IN ACC.OR DANCE..W..ITH CODE REQUIREMENTS ee..
...............................REV. 2........... 18/79 e
06/
- Sv57EM8 CLEAN UP DEMINERALI7E.
e 150 40.8 JC P.19426 OYSTER CREEK, UNET 1
. OttPAero 9Vs H. LLOYO DATES 05/02/74 e
T l...............................................................................RE?tEWED MY8 N. HOLLANO DATE8 86/ 0F/7 8 I
l vAtvE 8 TALUE NUMBER
- CLASI COi*O C&TE30*Y ST7E WALUE AC T. NotM.
TEST TEST
..............................IMATE......A....C.. D E....(.I N S.......E.....TY P E.. PO S........O ut.! NG.....
3 TYP REM ARES M
V16-63 1
G. 9 x 6 GA N
LO 1
OC-1 l
i i
l l
l l
}
1 i
4 1
Au i
3 I
I la**199EOs H.H.
AS(wfTM. CMgrr lENGINEEe nafra 14/24/79 PAGE 9
i
.,s 4
1
-~
m M
._< w w.vyrrm2y-9pe efe gg7*N+%,
n it
+
T T A 9 Lf 3 esee.eenseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.0..V AL VE SFOR WHICH RELIEF IS 9EING #EQUE
.eeeeeeeeeeeeeeeeeeeeeeeeeoeoooooeoseeSTfDoo e e e e eo e o o o s e e e e e e e e e REW. 2 06/10/F 9 e eee e eeee eees e
- SvSTE"4 f:L E 4 N-Up DEN!!C+ A L I ZE9 I S D NO. 8 JC P-19426 OYSTER CREEKe UNIT 1
. SCE* 4 pEO iv t H. Llov0 1 ATE 05/32/78 e
i.
REWEEWED BYS N. HOLLANO DAT 46/0F/T4
...................................e..................e................
....e...................................E:
VALVE
- v4LVE NUMer?
- CLASS C00ei CAf!G04Y SIZE VALVE
- ACT, N0tn REASON FOR TEST! kG
- e TEST TEST REQUESTING TO B E o
TNATE A9CDE INI TY TVPE P 05.
DURING NETHOD E XENP TION seceses s e es se e e e eee ee eee ee ee e e e e e eee ee e e e e e e eee ee eee e e e e( e eee ees e.PE.....
ee eeeeeeeee eee ee ee ee eee eee ee e eeee e eeeeee eeee e ee e *PERFOR ME
- ses se o o vi s-1 1
6 GA MO O
EF-1 E-5 NOTE 1 EF-3 ET-1 E-5 ET-2 1
EF=4 v16-2 1
g-3 v
6 GA M0 O
EF-1 E-5 NOTE 1 EF-3 ET-1 E-5 ET-2 l
1 EF-4 W16-16 1
4-1 8
6 GA 40 0
EF-1 E-5 NOTE 1 E F-3 ET-1 E-5 ET-2 1
EF-4 vie-61 1
G-3 4
6 GA MO O
EF-1 E-5 NOTE 1 EF-3 i
ET-1 E-5 ET-2 1
EF-e 4
- 16-62 1
1-5 x
6 CK SA I
EF-1 E-6 NOTE 2 EF-3 vi6-e4
?
J-11 Y
70 CK SA EF-1 E-5 NOTE 3 NONE i
a i
4 A8Pu vE08 H.4 4S(WT7H. C4!"r EW,TitEE S 047rt 10/ 24/ F 9 PAGE 1G
gi TA 54: CLAD!FICATIGE OF REQUEST FOR RELIEF cesessese ss ess e e e s see s eess e s s e ee s ess ee ee e e e e ee% F oos eeee e e e e eee e ee e eee eeee ee eeeeee e ee eeeee ee ee ee e e e...............REV. 2.............10 / 7 06/
e
.....see
- SYSTEMS
- LFSN-Up XMINFe ALIF E 4 e
ISO NO.3 JCP*19426 OYSTER CREEKo UNIT 1 e
e
,'e OCE*ARED avt P. LLOYO DATE 85#02/F8 stEVIENED SY8 N. HOLLAND DATE8 06/0F/7 4 e
eseee eee e ee e ee e e ee eee e ee eee s e s es e ees es e e e e e eeoo es seee ee e eoos eee e e eeeeee ee eeeee e e ee eee ee eeeee eeeee oo see e
e o
NOTE VALVE NU14Ee e
RENARKS e
o e
seeee ee e e ee e ee e s se. o
..e.o o..ee e. e..............eeee..o ooo o ooo o s se ooo oe,... ee ee.oeos eese e, e eee e e,oese e,e eee e e eee e, e e e e s,eo e se,, e e
1 vi6-1 CYCLTNG THIS VALUE OURING NORNAL OPER ATION COULO CAUSE LOSS OF SYSTEM FUNCTION.
v16-2 THIS COULn WESULT IN WIOLATION OF CNEMISTRY ANO R AOI ATION LIMITS.
916-16 V16-61 v16-62 W A LV E C A NNOT SE RE VERSE FL CN TESTED OURING NotMAL OPERATION OUE TO INACCESSIBIL-ITV. ogygeSE FLON TEST GURIRG REFUELING l
l'
'l vi 6-8.
TNTS WAL VE SOFS NOT OPERATE UNLESS UPSTREAM 4ELIEF W ALWE (W16-F68 LIFTS. WALWE FUNCTIONS TO PREWFNT PASSAGE OF CONTAINMENT ATNOSPNERE FROM THE TORUS.
i I
As**0WE O S H.54 A M W IT H, fMIE F E NGICEED DAfet 10/24/79 eAGE 11
.n.
, :~
t e...............................TAGLE 15 VALV*S 9EING TESTE3
.I N A C.C OR CA NC E..NE T H CODE.. REQUIRE ME.NTS......
......................,..06/18/79 REV. 2 o
..........e
- 975T**e HvntauLTC CeNTRSL UNIT (TYPTCAL OF 1379 ISD No.8 JCP-19429 OVSTER CREEK. UNIT 1
- P3EP48E0 9V8 4 LLOYO DAT*4 05#01FF4 e
REVIEwt0 sys N. HOLLANO DATE:
.............................................................................................................. 86/06/74 VALVE
- OALVE MUMBE R
- CLASS C0090 CATCGORY SITE VALVF ACT.
NORM.
TEST TEST e
e aEM AR oes.............
.............TNATE...A. 8..C. 0.E....(.149.......E.... T Y. P E...PO S........D. UR..I N G.. M. E. T H TYP 132 2
Wa9 X
I.9 40 SA C
40-1
- U*TutE DISC TESTES IN ACCORGANCE WITH IN V-36 28.
A8PPOWfDS H.H.
A STW { T H, CH! F E4GINEES DATES 14/24/78
- AGE 12 i-
.,,,.,;. ; 3 s a,
.+
+
1, I
o.o.
.................................T44L.E.3e.....L.VES FOR uMIE.N 4E. LIE.F......
...E..! 806..REQUE.S..TE 0......................Ev. 2......... 6/18 VA IS S R
0
. SVU fM8 mfd.aulTC CONTWCL UNIT (TY8tCAL OF 1378 ISO NO.s JCP-19429 OYSTER CREEK, UNIT 1
- P*E*AREO 9Y8 P. LLOYO DATEt 05#81#7A REVIENED SYs N. HOLLANO 86/ 86/F 4
.....................DATE8 VALVT O VALVE NU49FD
. CLASS CO3RD C AT E4047 SIFE VALVE ACT.
NOR M.
TEST TEST REQUESTING TO BE REASON FOR TESTIIIG
- l l
..............................TNATE.....A........E......(.I N l.......T YPE.......T.YP E. P OS...... D RCD P
121 2
C-5 8.5 GA 5
C EF-1 E*F NOTE 1 N OIGE
=
EF-5 E-F NosIE
=
128 2
C-4 W
0.5 GA S
C EF-1 E-F NOTE 1 NONE
=
EF-1 E-T NONE
=
isa 2
C-10 x
0.5 CK SA EF-1 NOTE 2
=
=
122 2
05 1
8.5 GA 5
C EF-1 E-T NOTE 1 N ONE
=
EF.1 E=F NOIIE 123 2
0*%
X 9.5 GA S
C EF=1 E-F NOTE 1 N OME
=
EF=1 E-T 880NE
=
127 7
G-4 C.F5 RG A
f4 EF-1 NOTE 3 EF-5
=
ET-2 126 2
r.-9 E
10 RG A
A
=
EF-1 NOTC 3 EF-5 ET-2
=
184 2
G-11 X
0.5 SC SA C
EF-1 NOTE 4
=
A SE NIT N, CHIFr feestaeEE# 04YEe 10/ 2a.p y 4 pAGE 13
,.g n.-
3.: %,%
1-0 ' ~ % % *-
-~ ~
.y / 7 VASLE SAS CL ooosseeeeeeeeeee ee eee eeeeeeesseeesosessesseeeeososessesse&4IFICATI0ee OF REGUEST FOR RELIEF REW Ze 86/18/ F 9 eee e ee e eso seeeee ee ees s e ee eeeeo ese.c o seeess e es se e e e eee e ee ee.
O eeeeeeeeeeeeeeese e SYSit ee t MfGY AOLIC CDestR1L UNIY ITYPICAL OF 137%
I S O 100. 8 JCP-19429 OYSTER CREEK. UNIT 1
- PetPatto 9ft H. Llov0 04TEt 05/31#T8 REVIEWED SYs M. HOLLA8e9 OATE 46 seees e e e eo see e e oso se eee eeeeee e e e eeeeeeee ee eeee ee sses se s seee eeee eeeeeee e
O e
e eeeeeeeee.
e 40Vr VALVE NuM9F#
e o
e RENARRS e
o eseeeeeee eee eeee eee ee ees.oes eeo s e eee e ee ee ee eooe s eeeee ee.o oee eeee eeeeeeese seeeeee ee o
...ee e s sse....ee........................*
e e
1 121 OIRECTIOes&L C0elTROL WALWES MAVE NO SAFETV FuseCTI0ee A000 FAIL IN THE CLOSED 120 POSITToas.
122 A WITMORAHAL SIGNAL canes 0T PREVENT ANY ROO FROBE WSCRANNING8 THIS 123 VALWE WILL RE TESTES ACCORDING TO TECH. SPEC. 4 2.0.
2 13 8 FAILue! 0F THIS WALWE TO SEAT IN THE REWERSE DIRECTION RESULTS IN A LOSS OF IN.
SERT GRivt WATER *L0es.
j IT IS THEREFORE IMOIRECTLY TESTED WITH EACH RODS EXER-CISE Fv0LUT!04 OURING THE COceT400 R00 SCRAP TEST PER TECM.
SPEC. 4 2.A-0.
3 12Y CONT #0L 400 ORIVE SCRAM INLET AND ENMAUST UALVES OPERATE IN COINC10ENCE TO 126 RA8IOLY INSERT CONTROL ROOS. VALVES MILL BE TESTES OURIIeG THE CONTROL ROD TEST #ER TECH. SPEC, 4 2. A=0.
4 106 TESTIIeG THIS VALUE DURING N3RMAL OPER ATIOct REQUIRES ROO SCR AseseING SO THAT TH SCRAN ACCuteULATORS NAY SE CHARGES. THIS WALVF WILL BE TESTED OURIteG THE *0N 400 SCRAM TEST PER TECN. SPEC. 4 2.A=0.
1 l
l t
a i
AmoonvEQ t H.H.
A S(W TT H. CHIEF ENGINEE4 04TF8 10/24/71 PAGE to
-n ~e w s s
- W it* E M %'e M ""-~ " *'- }M -
~' ' '
>p :vge
.re
.e.
n.
.p g,
y<-
.m
![ eee........................................LW ES SE.IIIG TES.T E.D I N ACCOR04 TIC.E NI.T H C.00E.. R 2.,.. 8 6 / 18 / T 9 Ta3LE 18 WA 4EV.
e Sv$T*"I CnNT*0L 801 0419E HVORAULIC e
e ISO 800. 8 JC#.19426 OTSTER CREEK, UNIT 1 e
VALVE
- VALTF NU8MER e CLASt C0040 CATEGORT SIFE VALWE AC T.
88044.
TEST TEST RENARK$
e 144T eooee............. ee...........E...A........E..... int.......E.... TYP E..Po.s.
9 :: 0 t
T vP auRING METHos *
......................................................e Ut5-29 1
3 G4 N
0 1
PW.1
+
APP *0 wie M.M.
ASEWITH, CHI N E80GINEE9 DATE:
10/ 26/ T 4 PAGE 15 f
~
t t ~sda
,, * * - he: '-J.*
1"
- e3
., s
- a -
I
p' n,'
f
, ~,.
fz TASLE 3e WALYfs F0lt WNICH RELIEF IS GEING RE3UESTED oeoeose ee ee e ee e e ee e ee eee eeee e e e e e ee ee e ee eee ee e eee eeee eeee eee eee e eeee REv 2,
suis /F9 e
4 eeeeeeeeeeeeeeeee
- SYSTE**
CCNT90L 900 0#IVE MYO44ULIC e
ISO h0.8 JCP-19426 OVSTER CREEK, UNIT 1 o POE*4*E9 'tys M. LLOYO SATE 8 85/81f74 e
e RE VIENED ST8 N. NOLLANG OATEs S W SUF3 seee.... e e e e s s ee e ee e e e e e.............ee e e e.oo.....e oe s ee e eee e e e e e...o o,.
e eeee. eeeeeeee eeeee eee....eeeeeee e.ooes,eoe,ee ssee e e
VALVE
- VALVE NU49F'
- CLASS 00140 CATEGORY
$1ZE VALVE ACT.
N0eN.
TEST TEST
- EQUE STING TO S E REASON FOR T ESTI NG
- e.
............ e.................T N A T E.............. D E.....(.I kt...eoeeeeeeeee..E....POS.
A9C TYPE TYP 004ING METHOD EXEnPTION PE RFOR sE D
- r
.ee eeeeee eee ees ocoe oe e eeee sseee ee e e e eee e ee ee ee e e eee V18-?4 1
M-5 W
3 CK SA EF.1 E-5 NOTE 1 E F-3
=
=
V15-2 T 1
E-5 X
S CK SA EF-1 E-5 NOTE 1 EF-3
=
=
l l
l 1
cape 0VE ns M.M.
A st u !T M, C641E s' EssGIssEEe GATFt 1C/2 W F4 PAGE 16 t, u. v w w. < s - >- u n 46 &
-s t'
.- - m TaftLE SA s CLA4tFICATIOct OF REQUEST FOR RELIEF e.
......................e seeeeeeeee esesses seee ee sssee e ee e eee eesse oe oooo o oeeeeee e eee eee eee REW 2.
06/14 /F 9 e
eeeeeeeeeeeeeeees
- Sv5ffMS C04T4CL ROC ORIVE MVD48ULIC e
e 150 40.8 JCP-19426 Ov3TER CREEK. UNIT 1 e
- E*Aeto 9Ye M. LLOYO DATES 99/01/78 o
e 4tVItteEO ST8 N HOLLANO DATEe 86/06/74 seeeeee e e ee eee e e ee eee eee eoe o ese s sese es s e e e e ee o,e eoeoo oo oooeseeee eee eeeeee ee eeeee ee e
o e
eeee eeeeeeeeeeeoos ee ee eeee ee ee e e
NOTE VALVE N'J 49 E' e
e e
AENARKS o
seeeeeess eeeeeee eeee.oe eeeeeeeee eeeeeeeeeeeseseeeeee eeeeeee.o ooes..
e ee.ooooooe ee 1
T15-78 SECURING THF CtB SYSTEM COULO IwA!4 INE OPERASILITV 0F THE CAS seECHA vi5-27 IVA*'It SCCupulATES IN THE #ECHAMESNS AhO SEAL OVERMEATING WILL RESULTD.
!$MS
'ME C#O SYSTEM CAN NOT SE SECUMD FROM SERVICE UNTIL 4EFUELING.
THUS I
A8P*SWf St M.H.
ASKWITH, CHIFF EleGIIeEE o nATE8 10/2e#76 PAGE 17 m -
m.'-
' }, %,k$ ki')
- h,y rh % 5 Y 'if
?. N45 -'
TA9tE 18 e..
..................... eeeeeeeeee.V.ALUES 9E!80G TESTE9 TN ACCORGANCE WITM C00E REQUIREteENTS.e e e e eee e ee e e 86/18/T9 stew eee e eeee eee e eeee.
O STSTtrMa FUEL 800L CCOLING e FILT847104 e
ISO too.s JCP-19430 OVSTER CREEE, UNIT 1 e
e
- DQFPAoEO 4Y 4 LLOYD DATE8 84p Ps/ 7 8 REVIEWE0 ST8 N. HOLLANO OATEs 86/05/F4 eseeeeeeeeeeeeeeeeeeeeeeeesseeeeeeeee.oeoeoeeeeeeeeeeee eeoseee.............................................................*.
VALVE l
- v4LvF NtMer *
- CLAST C0080 CATEGORT SIFE WALVE AC T.
NORN.
TEST TEST 8t E N A R K $
INATE A9 TYP TYPE P M
eoeeeeeee eeeee e eee eee eeeeeee eee e...... 0 0 E...E 14)........E
...... 05.......OURING...o o....E..T M0 0
..ee...ee......................................
513-F 3
r=7 x
4 CK SA 3
EF.1 FORMAR0 FLou TEST u!TH PUetP A, REVERSE
=
FLOW TEST u!!N PUNP 8.
510 5 1
J-4 X
EF-1 F0%WA40 FLOW TEST u!TH Puste-8, REVERSE
=
FLOW TEST WITH PUISP=A.
V18 11 3
H=4 X
4 GA N
C 1
PVat 1
I i
l l
l l
CF##CvFOs H.H.
A S(W IT H, CHIe F E NG T88EE
- DATES 1 C/ 24/ F 9
- AGE 14 3,
..-n, ua o& as s c-
' *' ^^ ""
x..
y
-v x T49tE 18 VALVES coescocoassooooooooooesecoee e ee e eeee ee e e ee e ee e eee e#Et esG TESTE0 10 ACCOR GANCE CI TN CODE REQUIT.ENENTS aEV to 06/18/79 ee e e e e e eee e ee e eee eeee ee ee e ee ee ee ee ee e e eee e e e eee e e e e ee e e ee e ee e e e e e.
eeeeeeeeeeeeeeeee Io Sv3 TEM 8 COtt $89AY e
ISD No.e KP-19422 o **EmaeEO 979 w. a utot o+t 04Trs 04/tte? A 4EWIEt889 avs N. MOLLANO DATEI 06/8F/TS e
coeecoce o ee e ee e e ee e ee ee e eee e ee e e e ee e ee e ee ee ee ee ee eee s....eee e ee e eee e e ee ee es e
...ee eeeeo ooooeeeee.........eeeee e eee eeee e e ee e eee e eeee e e
o v4LvE e
- CALVE NmtRE 9
- rLASS C0040 CATEGOev STFE WALWE ACT.
NO4M.
TEST TEST 4 E N A 4 Il S ecoeeeo. e ee e e e.................I N A TE.. seeeeeeeee.
ee.........E..eeeee...e..
A4C0E (149 TYP TYPE POS OURING ItETH00 *
...ee e ee e e e e e e e e e e eee e....e e e e eee e e ee e ee e e......e eee e eee e ee e e.
I' v28-31 2
H-19 12 GA MO LO 3
EF-1 3
ET-2 VF6-15 2
H-11 X 12 CA N
LC 1
OC-1 C20-4 2
H-11 W
12 CA NO LO 3
EF-1 J
ET-2 v20-2 2
M-12 Y 18 GA N
LC 1
OC-1 i
I vrs-s 2
H-s X
12 GA Me LO 3
EF-1 3
ET-2 V20* !
2 H-9 X 12 CA 4
LC 1
OC-t U20-32 2
H=7 Y
12 GA 40 LO 3
EF-1 3
ET-2 V20-34 2
H-7 4 12 CA 1
LC 1
OC-1 U28-72 2
G-4 W
1 GL N
LO 1
GC-1 v20-9 2
G-4 E
EF-1 F04WA40 TFST WITH PUMP NZO1C, dEWERSE TEST WITH PUNP NZ81A.
v20-16 2
G-7 x
e CK SA J
EF-1 FORWatD TEST NITH PUMP NZC14 e AE WERS E
=
TEST WITH PUMP NZG1C.
1 20- 74 2
G-F X 1 CL N
LC 1
OC-1 9YPASS VALVE A80U40 V2G-16.
3 W2 0- 6 5 2
F-9 w
EF-1 I
W20-17
?
O-4 Y
15 CK SA 3
EF-1 F0 tweed TEST WITH PUMP NZs34 gepoovyne w,w, Asrygtw. cut eF E% f MEE
- OATFt 10/ 24/ F8 8 AGE 19 p..
ntn
~-
TA9tE VALVES mEING T o eessee.** e ee s e..o ** e e moseeeee*14*
. e seeeee.
.o eeeeeeeee.o.
eeeeee****eeeeeeses.
o SYSTE"o CURT SPRAY e
ISO NO.8 JCP-19422 o DCEDAeF3 1Yt W.
GUSOLPH DATE: 04/2A/79 e
REVIEWED 878 N. HOLLANO DATE: 06 e
e seeeees.
.s o s*
- s e e. e.... ** o * *
- e s se e e e e e e e e s e e s s e e. e ee e eee e......e*e
.......................... ee ee e e e e e e e e e e ee e e e
o e
WALVE eeeee...
e ysty! MugqEe
- CLASS C0090 CAT 50RT S!FF V8LfE ACT e M34M.
TEST TEST e
TNATF A 9*
t INI TYPE TYPE Pos.
DURING REN AE ES oeeeeeo ee se=oe=e*******eseseoeoo eesee**,*O E* *
- e oo e ** * *o e s e **
- oo o ooo * * * * ** ee e ee e e e* ME THO D
- e***e**** e.ooveeeeeeeeoooo****eoo eeeeeeeee***
V73-9?
2 E-F W
1.5 GL A
0 3
EF=1 3
ET-2 3
EF*5 v20-96 2
E-F Y
1.5 GL O
3 EF-1 3
ET-2 3
EF-5 v 23-14 2
0-F X
EF-1 FORWARO TEST WITH PUNP NFO3C.
W 2 0- 9 2 2
C-4 K
EF-1 FORW ARD TEST WITH PUMP NZ834 REVERSE TEST WITH PUMP NZO3C.
v20- 53
?
C-7 r
EF-1 FORWARD TEST WITH PU9P NZO3C. REVERSE TEST WITH PUMP NZ834 V20-50 2
C-9 10 CE 1A 3
EF-1 FORWARO TEST WITH PUMPS NZO1CaA. REVERSE
=
TFST WITH EITHER PUMP h2034 04 C.
V 20- ?*
2 8-8 4
2 RL SA C
1 TF-1 ve0-??
2
- =4 6
GL 40 C
3 EF-1 3
ET-2 v?J e?
2 F-b W
EF-1 TEST WITH SYSTEM FUNCTIONAL TEST.
V20-17 2
8-5 Y
GA MD 0
3 EF-1 3
ET-2 V20-1*
1 C-5 W
4 GA M0 C
3 EF-1 3
ET-2 v?c-6e 1
C-4 v
9
- f. A 40 C
3 EF-1 3
ET-2 VFG-1*
1 0-4 W 6 GA 9
LO 1
OC-1 A**envros M.M.
AstwtTH, CMt:r ENG7 NrE e
- ATFt 1 ?/ 26 # F 9
- AGE 20
)
, p.
a
+
2-
, m..
TA9LE to V ALVES 9EtteG TESTED 14 ACC04 eeeeeeee e eeeeeeeeeeee eeeeeeeeeee eeeooo ese ee eeeeeeeeee eeeeeeeeeeeeeeeee=98MCE WITH COSE Rela;IREMENTS REV 2,
86/18/F9 ee e e e e e e e ee ee e ee e eee e e e e e e e e e e ee e e ee e e e e e e e e.
o eeee eeee eeee ee ee e o ST37FMt C0er So#A T e
e ISO NO.8 JCP-19422 e poEDAFID SYs W. CU90LP4 OATEa 34/28#'8 e
e REVIEWED Ovs N. HOLLAND OA 86/07/74 eeeeee. e ee eeo.. oo oe ee e....o oe..eeeee. eeeeeeeeeeee ee eeee.... eee eee.o.eeeeeee ee eeeee.ooe eeeeeeeeeeeeeeeee o
e VALVE
... e ee e ee e. o.ee e
- UALVE NUstV R
- CLASS C0040 CATEGoev STIF VALVE ACT.
NOR98 TEST TEST 4EN AR ES INATE A 9CDE TvPE TYPE POS.
OURING NET eeeeeeee...eeeeeeeeeeeeeee.......eeeeeeeeeeeeeeeo(IH..oo e eeeeeeeee eee ee eeeee...ee eee ee.H00
..e eee e ee e e e....... e ee. e o e e e e ee e e e..........
V20-73 2
C-11 Y 1 GL M
LO 1
SC-1 Utt-9 2
G-11 x
~3 EF-1 F04WA40 TEST WITH PUNP NZG1-8 REVERSE FLOW TEST WITM PUNP NZ81-0.
V28-22 2
.G-10 x
8 CK SA 3
EF-1 F04WA40 TEST WITH PU9P NZ81-0, REVER SE TEST WITH NZO1-B.
U28-75 2
G-13 u 1 GL M
LC 1
OC-1 SWASS ARCUNO v20 22.
U78-51 2
C-12 a
EF-1 F04Wate TEST WITH NZO1-8 AND De aEVE RSE TEST WITH EITHER NZ83-8 04 D.
W25 54 2
C-11 X
10 CK SA 3
EF-1 FORWA90 TEST WITH NZO3-3, REVERSE TEST WITH NZ83-0.
U28 11 2
Catt 4
EF-1 F04WA40 TEST WITH NZ83-8.
U28-95 2
C-7 1
1.5 GL A
0 3
EF-1 3
ET-2 3
EF-5 V'8-93 2
C-7 x
1.5 GL O
3 EF-1 3
ET-2 3
EF-5 V2C-5*
?
C-13 2
16 CK SA 3
EF-1 FORW ARD TFST WITH NZG3-D. RE VERSE TEST WITN N703-8.
V2 0- 19 2
C-9 19 C4 SA 3
E'-1 FO*WA4D TEST WITH NZO3-0.
W28-71 2
B-10 x
6 C4 SA 3
IF-1 U29-24 2
A-8 u
2
- L SA C
1 TF-1 Coe*CvFCs M.M.
4 5 N W IT **. CHI'*
ENGINEEO OATF1 10/26/'s oAGE 21 s
3r +s
,a
+
s.
3,w ; m-,
~._,
TAS oce.ooos............................LE...18...V2L..VES 9E I NS TE.S.TE.S.I3..AC.CORGANC E.C..I.TM CO.D.E e e.c.u !RE.MENTS..
..........REV. 2.e 86/18/ F 9.....
CE...
.oe.
.........ee
. eeeeeeee o
- SYSTEMS C098: 5884Y e
o 150 N0. 8 KP-19422 o carosegr3 w e u, eL30L*H DATES 84/FA/'S e
o 4E VIEMED SVt N. HOLLANO DATES 86/8F/F8 o oooooes se seeee eeeee eeeeess sess eeeeeeeeeeeeeeeeeeeeeeeeeeeeeesseeeeo eeeeeeeeeeeeeeeeeees oooseeeeess e
VALVE
- VALCF Nu99E9
- CLASS C0090 CATEGo4Y S!?F WALVE AC T e 9008tMe TEST TEST REMARKS o
INATF A 'l INI T
TYP E oece eee........e ee e e e e e e ee e e e e e e.........C 0.E.. e e( eee e ee.v*Eoeseeeee...P05 OURING METN00 *
....seeeeeeeeeeeeeeeeeeeeeen...................................
V11-109 2
9-6 X 2 GL M
LC 1
OC-1 U25-26 2
B-6 X
6 GL MO C
3 EF-1 3
ET-2 028-31 2
F-5 x
6 CK SA 3
EF-1 TEST MITH SYSTEM FUNCTIONAL TEST.
l vr8-18 2
A-5 X
4 GA MO O
3 EF-1 3
ET-2 U28-21 1
6-5 4
GA 40 C
3 EF-1
\\
1 3
ET=2 U28-41 1
A-5 X
8 CA MO C
3 EF-1 3
ET-2 V29-F1 1
4-3 2 4 GA 4
LO 1
OC-1 I
C8P#0 Kit H.H.
A Ss(W IT H, CMIFF ENGINFE0 DATFt 10/ M/78
- AGE 22
TacLE 3 v4LvFS F0 e.
eeeeeeeeeeeeeeeeooeeeeeeeee...eeeeeeeeeeeeeeeeeooes.9 tsNICM RE. LIEF IS SEING REQUESM O O
.........eoe eeeeees e.ooeeeeeeeeeeee.oooe ooseeeeeee#Ev. 2.
06/18/r9
- SYSTEMI C04' So*Av e ees se e...s oo e o ee ee s e
ISO 4Ce t JC P-1 % 22 e
e pcEpAgro gy: w euo0LPH 04TEs Se#28/F8 e
REVIEWED Mvs N. HOLLAND 04TEt 06/ 0F#T S e
seeeeee e e ee e ee e e s o s ee ee e e e e s s e e e e e e e ee e e ee s e s s e s s e ss VALVE
.oosee,eeeeeeeeeeeeeeooseeeeeeeeeeooseeeees oeoo,se*
- VALV! NU19F0
- CLASS C0000 C&TEGORY SIZE Valvt ACT.
NOR N.
TEST TEST REQUESTING 70 et e
o REASON FOR TESTIDEL
- TM4TE 49C1E ttM TVPE 8 05 S UR th G METH00 EKEnPTION PE RF OR MED ees ooe.oeesesseeeeeeeeeeeeeeeeeeeeeeesseeeeeeeeee. eoeeeeeeeee*TVPE
- e coooooooooooo.
470P-A o ss e s eoo o o o o o s e s s e ee. c o s e s e e e e e 1
4-t x
CE A
C EF-1 E-5 NOTE 1 EF-2 N702*C 1
EF=6 1
0-3 r
4 CE A
C EF-1 E-5 NOTE 1 EF-2 NZ87-9 1
EF=6 1
%.?
W 4
Cg A
C EF-1 E-5 NOTE 1 EF-Z N287-9 1
EF-6 1
1-1 N
8 CE A
C EF-1 E-5 NOTE 1 EF-2 1
EF-6 I
}
}
l l
i i
I l
l l
I I
l l
l
' APPSCWrol W.H.
AS W ITH. C641EF
}E**SINEED f14TF 8 13/24/?9 PAGE 23 4.., usa-n-
- 444 C ' * -
'~~
c~.y gru, agiw
.~.
_~ 7
<m, t
..........................................T A GL..E. 34 0...S t..e4..IF I SA.T.I.S.I. 0F...R.E.G.U.E.S.T. F 04.. A EL..I E.F.
.....................E.W. 2,......G 6./18/ F 9 R
- SYSTEM roer speAY ISD N0.8 JCP-19422
- P*Ep At*0 BY t W. Run0LPH DATE: 36/24(7s e
REVIEhEO BYs N. HOLLANO DATE: 06/
.........................................................................................................................0F/F4 NOTE VALVE NU9tEP o
R(p44(3 e..................................................................................................................................,
1 NZO2-A THIS WALVE RE0ut9ES A ZERO DIFFERENTIAL ptESSURE ACROSS THE VALWE DISC FOR IT TO NZ32-C 4E STRDEED IN THE TEST N00E.
THIS REQUIRE PENT IS SATISFIED IN THE COLD SHUTD0lme l
j M702-0 CONDITT O N.
NZ 'J2 8 3
i f
l l
l 1
i t
ii l
i l
l APP 90VE08 H.H.
ASKWITH, fM!is EssGINEE # OATFt 10/24/79
- AGE 26 f
.o TARE is valvtS 9EING TESIED It e.............................. e e e e e ee e e s.oo e s e oo o s see e ee e.3.A C.C.OR.O.P.NC E.t:I..T H C.00.E.CE.Gu ta.t. tee.NT.S 8t EW. 2.
06/18#7 9
...........eeeeeeeeeeeeeeeeeeeeeeeeee e
e
- %YSTT48 # FACTO # NEAD CO3 LING e
ISD NO.8 JCP-19426 QVSTER CREEK. UNIT 1 e
o OpFRADEO 978 M.
LLOVO Oafts So/28#F9 REVIEWE0 SVt M. HOLLANO DATES 86/06/F8
- e............................. e e e e e e e e e e e e e e e e e e e e e e e e e e e e e.o o e...............................
e VALVE
- WALVE NUMER
- CLASS COORD CATEGORY S!7E VALWE ACT.
NORN.
TEST TEST RENA8KS e
e gNavF A9CDE t TV8 TYP SURIkE METM00
- e.................................................INI.......E....... E... PO S.
....e e ee e ee e e e e ee e e e e e ee e e e e e....................................
V31-P 1
0-9 Y
t GA A
C 1
PV-1 v31-5 1
2-7 4
2 CK SA 3
EF-1 REVERSE Flow TEST ONLY.
I l
4 8P4 0f r 0 s H. M. ASatu!TH. CHIrr ENG!CEE8 MAfft 13/24/71 PAGE 25
n-7 y
............................. T. A %. E.1 1....L.W.ES SE..ING TE.S.TE..D IN AC.C.Ot 0.A NCE..W.I TH C00E RE..S.3!4ENENTS.....................E..v. 2e.....
86./10/F9 v4 R
o SYST**s gA Tas S TEA M ISO tec.s JCo-19423 OVSTER CREEKe UNIT 1
- MfPA48D 978 W. #U90L8N DATE 45/OS/F8 REVIENED 9V8
...........................................................................................N.
HOLLAND DATES 86/87#F 4 W AL VE
- 1&Lft MUNif2
- CLASE C0040 CAT'GORT
$17' WALyf ACT. NotM.
TEST TEST
..............................INATF...A..R C D E....(tul........E.... T Y P E... P0 3........C. UR..I h G..... E..
Ne-261 1
C-E w
6 RL SA C
1 TF-1 40-296 1
C-9 X
6 RL SA C
1 TF-1 N*-28C 1
t-S r
6
- L SA C
1 TF-1 n4-299 1
C-4 X
6
- L SA C
1 TF-1 l
N*-29E 1
C-4 4
6 RL SA C
1 TF-1 co-29r 1
C-3 4
6
- L SA C
1 TF-1 i
co-28G 1
C-3 6
- L SA C
1 TF-1 1
NS-FAH 1
C+11 1
6 DL SA C
1 TF-1 N9-24J 1
C-12 4
6 RL SA C
1 TF-1 l
NS-24E 1
C-12 X
6 DL SA C
1 TF-1 i
ko-29L 1
C-11 E
S RL SA C
1 TF-1 N*-PS*
1 C-11 6
RL SA C
1 TF-1 d
4 co-PSM 1
C-10 X
6
- L SA C
1 TF-1 4
me-29*
1 C-13 Y
6
- L SA C
1 TF-1 A*P*19*Ce M.w.
aSrw!TH. C'41 F ENGINEfe OAfra 19/'brFS PAGE 26
,.. 3:w a--<;
4 789 VA o
...............................L.E..il.....LVES.. met t0G TESTES.IN ACC..ORDANC E WITM CDCE. REQ.u!4E.NENTS REv. 2, 36/18/ F 9
..................... eeeeeeeeeeeeeeeeeeeeeeee.ooeeeeee...
e
- SYSity : Malg STEAM e
e ISO se0.s JCP-19423 OTSTER CREEK, UNIT 1
- 94 epa *ED 97 W. GU30LoM OATEs 35/38/F4 e
o 4Ev!TWED Svt M. HOLLANO DATE8 86/ 0F/7 8 e eeeeeeeeeeeeeeeeeeeeeeeeeeee.....es...................eeeeeee...............................................................e WALVE e
- CALVr NU99F o
- CLASS C0090 CATEGORT SITE VALVE AC T e N64M.
TEST TEST It! A TF A 9COE I I49 Typt TTPE OURING NETH00
- AENARES eeesseeeesse........eeeeessesseeeeeeeeeeeeeeeeeeeeeeseso ooe eeee POSese o o oo o o o se e e eeeeeee ee ee K9-280 1
C-9 X
RL SA C
1 TF-1 MQ-298 1
C-6 4
6 4L SA C
1 TF-1 8:D-1984 1
0-4 5
6 RL E
C 1
TF-1 THIS IS AN ADS VLW. AND WILL BE TESTED IAW TECN. SPEC. 4.4.8.
N*-1084 1
0-4 2
6 RL E
C 1
TF-1 THIS IS AN AOS VLt. ANO WILL BE TESTED IAW TECH. SPEC. 4.4.8 C2-108 C 1
C-9 4
6
- L E
C 1
TF-1 THIS IS AN AOS WLV. AND WILL SE TESTED IAW YECH. SPEC. 4.4.8.
no-1099 1
C-9 Y
6
- L E
C 1
TF-1 THIS IS 4N AOS WLt. AND WILL BE TESTED IAW TECH. SPEC. 4.4.8.
MS-189 E 1
C-7 2
6
~8L E
C 1
TF-1 TAIS IS AN ADS WLv. ANO WILL BE TESTED I4W TECH. SPEC. 4.4.8.01-107 1
E-6 2
GL MO C
3 EF-4 t
3 EF-1 3
ET-2 01-1 !6 1
E-4 Y
Z GL RS C
3 EF-1 3
EF-1 3
EF-2 V1-118 1
H-F W
2 GL 90 C
3 EF-1 x
3 ET-2 1
EF-4 h
/
APP *0VED: 4.4 A S(W TT N.
CHI? 8' tieGitrE' OAfff if/24/T9
- 4GE 27 ip
. ~, w w.c h inw'm~
"" ~
b
. +
~
TasLF 5 8 VALVES FOR NNICN RELIEF IS SEING REQ cooesseeeeeeeeee ee eeeeee eeeeee ee eeeeeeeesseeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeeee.ooe UESTEDe.ee eee eeeeeeee RE V. 2.
86/14/7 e
e 375TF48 MAIN STEAM o
e ISD NO.8 JCP-19423 OYSTER CREEK, UNIT 1 e ergoAego sy W.
R u.10LPH DATE8 SS/04/F9 e
e REVIENED 978 N. HOLLANO DATES 86/SF#Fs osoeee e e e ee eee e e e ee ee ee e eee e e e e e e ee e ee e e ee e ee ee ee sses se ee sseeeee e ee e e
VALVE
- VALVE qu1ste e CLASS C0083 CATEG0tf SIZE VALVE ACT.
N04 M.
TEST TEST REQUESTING TO SE REASON FDR TESTI NG
- oe s........................... e e e e ee e e ee e e e ee e e eee e ee e( e eee eee e e ee ee ee ee ee.oo e e ee e.
eee e ee ee e ee eee ee e eeee e e eeee ee e eee ee e eeee ee ee ee ee.
V1**
1 F-7 E
24 GL A
0 EF-1 E-1 NOTE 1 EF-2 ET-1 E-1 E T-1 EF-5 E-1 EF T
~
1 EF-4 V1-7 1
G-9 Y
24 GL A
0 EF-1 E-1 NOTE i EF 2 ET-1 E-1 ET-1 EF-5 E-1 EF-F 1
EF-4 v1-9 i
H-15 tb GL 4
0 EF-1 E-1 NOTE 1 EF-2 ET-1 E-1 E T-1 EF-5 E-1 EF-T 1
EF-4 V1-10 1
M-18 1
24 GL A
0 EF-1 E-1 NOTE 1 EF-2 ET-1 E-1 ET-1 EF-5 E-1 EF-7 1
(F-4
- 1-111 1
4-8 y
2 GL M0 C
EF-1 E-5 MOTE 2 EF-2 j
ET-2 E-5 ET-2 1
EF-4 4
1 4
A**80 rE O s W.M.
AS<WITH, CH!rF E NGI%EF
- OATE8 10/76/79 PAGE 24 n
e-e_
e-
r Taste 3As CLARIFICATION OF REQUEST FOR RELIEF
- seeeeee e e ee e ee e....o e e s e ee ee e e e e e e e e ee s s e ss e e e s se ee e e ee e e eee ee SCW 2,
86/18/T9 e
e e e e e e e s se ee ee ee s O $"JST E N 8 MATM STEAM e
130 NO.8 JCP-19423 OVSTER CREEK, UNIT 1
- FCEeAREO SYs W.
euq0LM8 OATES 15/08/78
'j. e 4EVIEWEO 878 N. NOLLAND 04TE8 96 e
eeoesee ee eeeeee e ee eee eee eeee eee e e eeo oo ooose ee ee ooseeooe eeeseeeee ee oooesee o
o e
o e ee oo se se e e
NOTE
=
vaLVF N'IMS t e e
' +
RE4AR45 e
e o
esoseeee e ee eee........e c e....ee e eee e e ee e s o.o........e e.e eee eee e e ee eeeooe ee eee.e ee eeeee e.o e
l
..e 1
11-4 CYCLING 8*8ES VALVE QURING NORMAL OPER ATION REQUIRES Rf00CTION IN POWER. V V1-7 WILL OE MRTI AL STRDetES DURING NORMAL OPER ATICN ANO FULL STROKED AT COLO V1 -9 SH UT0eente I
V1-10 l
t F
v1 -111 CYCL!acG THIS VALVE OURIIeG NORM AL OPERATIO84 WCULO A04tf HICH PRCSSURE STE44 TO THE MATM Cole 0EMSER ANO COULO CAUSE LOSS OF SYSTEN VACUUM.
i I
l I
i i
1 4
I l
A ppe07E f): H.H.
A SK WIT H, 04tiF FNGIDIEtt GATEt 10/ 28e/ 79 PAGE 29
~.
er...a ns.
>r i:, +
~~-+~n'+-
,,r.
l TA3LE 18 VALyt1 SE esseeeeeeeeeeeee ee e eeeeeeees e.oe seeeeeeeeeeee soseseee!NG TESTED IN ACC0ft949eCE WITH C09E PEtu!REMENTS essee o oooooseeeee eeee eee ee ee e e eee e eee oo eee eee e.ooo oe eee e *E W.
Ze 46/18/79 i
e e e ee e ee e e e e eee e ee ee e
- SYS T!'It FEE 9WATC#
i e
e ISO aIO.I JCP-19426 OVSTER CREEu, unti 1
- Derp A*E3 siv e W. RUGOLPN 04TEI 35/58/F4 o
e 4EWIEMEO OT8 N. N0 DATES 86/09/F8 e
e oesee e e ee ee ee e e...e e........e e e eeee e e e e e e e e e...eeee ee eeeee eeee eee eeeeee ee eeeee ee e
VALVE
.......... ee.....ee........
i
- VALVE NU9 tit
- CLASS C0090 CATEGORY S!?! WALyt AC T. N0tN.
TEST TEST e
e It E a a e e
t e..........................IMtTF.eeeeeeeeeesD E
A4C o o e s s e e e e ee e e e e e e ee e....O.S..e...S. UR..IN.G.. 80E. f ae0 t 140 TYPE TvFE P l
.ee.........eeeee V2-35 i
C-6 X 14 GA 4
LO 1
OC-1 l
V2-36 1
0-6 x to GA M
LO 1
OC-1 t
h i
t i.
l 1
l l
l
{
e t.
I l
c 1
?
L
['; AP*#0VF Ds St.H.
A S KW IT H, CStI!F l
E88GIsotte SAir i c/ 2h rF 88 PAGE 3;
.c z
. A:, :.p -
,.y 'ti.
S i' - %% 5% *'
- A ' C '" W%+ ' ' ' '
meme-_m -.,,_
I
7 7'~-;~,.,
)
FABLE 18 VALWf S FM WMICM eeseeeeee ee sese s ee e ee eee eee e e ee e e eeeeess es seee e ee eeee ss e seee e eee e ee#ELI EF IS SEING etGUkBTE S SEW 3.
8 6/18/ F 9 e e e e ee ee ee e e e ee ee ee e ee ee e e e e e e e e e ee e e e e e e ee e ee e e.
e eeeeeeeeeeeee....
o SYSTE N s FEF owA TFe e
e ISO 40.3 JCP-19426 OfSTER CREEK, U4tf 1
- PCEPARED 978 W. #UGOLPM DAFT 4 05/04/F8 l
ILE VIENED N. H3LLAND DATES 86#95/T8 eeeeee ee e eeeee e e v essees ese.ooo s seeeeeeeeeeee ee eeeeeeeeeeeee eeee eeeeeeeee eee eeeee l
VALVE
- V8LVE NU1RT*
- CLASS C0380 Caf(GOWT
$12E VALVE ACT.
h0RN.
TEST TEST
- EQUESTING 70 et e
REASON FOR TESTI NG
- Iha eee.ooe e e ee ee e e e e e e ee eee eee e ee e e e e e..tF A il C D E IINS TYPE TYPE POS SuethG NETH00 EsEMPT
.eeeeeeeeeeeeeeeeeeeeeescoeeeeeeeeeeeeeeeeeeee.eee e e eee ee e e ee e e e e ee e e ee e ee e e.I ON PE RF M ME O
- l
..eeeeeeeeeeeee....
V 2-71 1
3-5 m
is C4 SA t
EF-1 E-5 NOTE 1 EF 2 i
W2*72 1
0*5 W
18 C4 SA i
EF-1 E-5 NOTE 1 EF-2
=
r l
V2=FS 1
5-4 W
in C4 SA l
EF-1 E-5 NOTE 1 E F-2 U" "
1 0-4 X
18 C4 SA EF-1 E-5 NOTE 1 EF-2 A***0VFOs M.M.
454WITH, CHIIF ENGINEF # DatFs 13/ 26/ h 84GL 31
- u -..;w, - ;s t
-W co-
-k+-
"~
09OeGGGGS46 h.
h, l
\\
e l
S* 9
- 4 e
w e
1
- 9. G tw e
e
%9 to 9
6 GG M
um 9
e se e E
4 6
6 I
%e D
O O
M d6 as e
e end e se e e
e G
9 G
W G
9 4
e see es e
e 2Og ee taf taf G
G 848 9 W
to e
e taf >=
0 0
4 9
9 taf 3 es O
O e
bg he M
O O
taf G hp 9
9 4
ge e
e CD e
WD e
e J
G e
e MO 6
O O
e e
@U e
E 6
e D
e 4
e e
.A a.m i
e
.a e
e 2
e 9
9 4M 49 e
6 6
She 9
e E
9 4
9 4
M 9
e e
O O
ee R
O e
MO e
9 9
e > tal e
e e
A>
e a.s
= o e
3M e
"b
> e e
M taf G
G e o
taf to e
e D
e e
a e e
3 9
e es e 6
EO R
tw 3
e M
9 OJ e
e me en.
46 me 4
W e >
taf e O > e e
4 bl De O M
quf 9
E
$ 99
.A e sus W e
%f F he e 4
9
& the NO e
e OD 0
E O
ef 58 3
W*
- 40..
m.
6.
O 9
O S
P9 e= e e
e WB $
9 9
J tan e O
O J
nef
,.p 39 9
WM Oe e
O 83 O
4
~
gG g
we w
e E lap S
6 9
9 G
g>
bI 1
d 3.
m O..
e 9
af M De 9 9
6 hM 2
>e 9
e 3
ge 6
e
- g. -
u4 e
e to
", e ese e e
e t=
tb O 9
9 4
- De 4 e
S&
-r W9 4
e eO 4e o
e tie t=
t_
Je e
e es. 4J E6 o
O tb 4 e
D G
tad O
e e
49 &
s' eo e
o y
^*
e8 e e
e M b3 8% e e
e WX 0
9 9
g>
tmE O O
e w
.A e e
e las O f'
to 4
e e
Mm Se D.
e
>e 9
9 I
e e e e
e es G
e Of 1
G e
e O
.en eeeeo v,
e e
o D
Q 9
e.'e' 6
.e
.o m
w 0.
e e
e e
4 e
e y
e o e e
N' O
k 6
e o
the e
b o
O 9%
e a'
9 9
Y e
e D
?
e en O
E O
E e 6.
e
& e e
M I-O J
O O
3*
o C
e an, e
we ens >= 3 t.s >m L
O O e 9
Om em 9m Sms 3
9 J
G
$ 0 9 0 1N G
e k
e em o
N ed N ee e
he e
D e
D>>>
e to e
O M *1 s
3 es e
4 3
e e
e 3
9 e
h t
e C
eoeeo er.
e be en o
e e
t-e t.a t-e o
op e
es e e e
e to
[o e
e O
t>
e Q
8 e
e4 e
4mA 9
Gn2 9
ZO 4.
e 3
y e
> e ce e
b, 4
e ta e en O
t=
4 X
D Oa 6
M 43 8 e
e he las e
> m e
e 95 tal C2 e
M g
e e
l' s
e e
ae-
~
6 9
9
&q
)
9999999 $#94 LE k^
4 Inf
-~
[
s
i I
l 990$$0006eo 2
W N
o taf tai y
.G Ep
.=
t.al taf
- 9..
.P W
('9 E
.r.t g
3 3
S e
d
.e e,
d 9
.o.
E E
M S
3 3
.I.e g
.o d eso E
t 3
o N
.O U
w 3
3
=
er g
g g
g d a 3
a 2.
e 5
)
taf.
.taf E
E T
.E.
3 6
=
w e
.e e.e m.
T
=
=
=&
B.
E 3
3 t
T O
W.
.B.
3 M.3
.=
Las
.=
l 2
of
.In.f
.had
.Ia. &
W w
. tai
.te
=#
l 9
4
.T
,T T
=
3
.,te f
=
=
5.e E 8
3 o
a
=
s
=
o s
s s., - a-
.s
.s o
s
,s,,
. =
-. =
O o
o w ow o
o u.
4
.a
.a v.
.a W
s
=
=
==
=
t w.
w Ec no O
o o
o s ss w.
o
.o m
s
==
g
.o l
St Vw I.****
.o o
W w.
a.
us m
v.
w w
w w
ow ow -
3
- 1..
o
.s w
.5 3
W a
8 5
v.
mm
+
o oF a
e a
u a
o o
a o
a a
a
=
.a..t 3
.w
~,,
.a.t
=
r r
r
,v t
W
.s
.M
.v
.v
.v s
w
+
o.
.u 9
o o
o aT 5
~
~
. ~
~
w.
1' i
.s w
=
1
.w=e.
.s. o...
~
~
t
..-c w.
u.
.s.
o.
.ir
~
o
~
~
o u.r w
o r
w e
u o
a v
.r
~.,
i n
m m
s o,
.s.
u.s O,
c s
3-s
-.s.
s
=
2 e
t
.c,.,
2
- r. -
.c.
se
=
w
.a e
e.
W s
r
- i..
or 1
i a
- - - ~ " ~
A.
4
^<
T e................................. A g t E.1.... v 4 L. V ES. 9E I NG.......E.S T E. S I N A C.C 04 0A seC.E.. W.I.T H C.O..DE..M T
e
- TystE=
CONDENSAfr TRANSFEe e
ISO loc.e JC8-19424 OVSTER CREEK, UNIT 1
- PPEPA*En 4YS
- 4. LLOYO dates 05/02FF4 (E WIEWEG STs N.
HOLLANO 86#87#78
.................................................................................................................DATE:
e e
v&LvF
- UALVE NU94E R
- c1ASt C0090 CATF".0*f STFr VALVE ACT.
esotN.
TEST TEST R E se A R K S
.............................INATF..........................L.....E.....S.........ING......................................................*.
A9CDE (14) TYP TYP PO DUR stETHOD
- I' l
V11 37 3
J.9 y
3 CK SA r
3 EP-1 TEST WITN v11-17.
V11-39 3
K-9 4
EF-1 TEST WITN v11-17.
W11-14 3
A-10 W
2.5 CA A
0 3
EF-1 i
l 3
ET-2 I
3 EF-s v11-31 1
A-9 2.5 CC 4A 3
EF-1 VERIFY OPENING SY PROVING MA KE-UP TO ISOLATION CONOENSEP V11-16 3
A=11 x
2.5 CA A
0 3
EF-1 3
ET-2 3
EF-5 V 11-25 1
A-12 N
FF-1 wet!FT OPENING SY PROWING MAKE-UP TO ISCLATION CONDENSER l
APP 904 fos H.H.
A S K W TT H, CH!rF ENGTNEES 9ATEt 10/24/Fe
- AGF 3b g
n,
=. - -. -
TABLE 18 e.aeosoose.ooooooeeeeeeeeeeeeeee.eeeee.e.. 94 LUES 4Ef 4G TESTE913 ACC.0e0AneCE CITM CODE.#EQu!!E..ME
.......EW. 2.
06/18/79
.eeeee......seeee.oeo......e.ee........
o e........e.ee.......
o MrSYrNa SrPVICF e E'tERGENCT SEeWICE MTR.
e o
I S O 40. 8 JCP-1942F OYSTER CREEKe UNIT 1 o P*E?ADED ive H.
LLOYO 08tEt 05/01/T4 e
e 4EWIEwf0 nys N. HOLLANO DATEI 86# 8F #F 8 ococo e e.
...... e...o o e... eeee s o.o e.o o es s e e e s s s ees e es s e eee s see eee eeeeee ee eeeee ee eeeeeee ee eee eee e 6....................eee.
l e
o e
VALVE o g4LCE Muggte e CL4SS C00e0 CATEGo#Y SITE v4L 4E AC T.
100eM.
TEST TEST e
e aEN AaKS r
eso..........................IMATE...........C..n E. e e...... e e...E.....TY PE..e.O.o o..eoo...IhG A 8 (14) TYP PS Oust 8eE FN00 *
......ee.eee..........................e...............
V3-6 2 3
E-6 x
EF-1 REWERSC FLOW TEST NOT RE00!9E0 IF B0tM
=
SERVICE WATER FusePS ARE OPERATING.
v3-6 3 3
F-4 4
16 SK SA f
3 EF-1 AEWERSE FLOW TEST NOT REGUIRES IF SOTN
=
1 SE4WICE WATER PUstPS Att OPERATING.
F U3-5 9 3
8-4 Y
20 SF M
C 1
PW-1 03-152 3
F.6 w
2 CA N
O 1
Py.1 V 3-134 3
F-4 W
2 G4 N
O 1
P W-1 V 3-131 3
F-6 8
2 C4 SA 3
EF-1
=
C3-133 1
F-4 a
EF-1
=
v3-tb9 3
F-5 X
2 GA N
O 1
PW-1 W3-112 1
F-6 4
2 GA N
O 1
PW-1 91-134 3
F-8 Y
Z G4 M
0 1
PV-1 v3-55 3
F-7 x
EF-1 FO4 WARD FLOW TEST WITH PUNP 523, #EWERSE
=
FLOW TEST WITH PU9P 52C.
03-66 1
F-4 E
EF-1 F0auA40 FLOW TEST WITM PUNP 52C tEVERSE FLOW TES T WITN PU9P 570.
W S-f F 1
F-9 s
13 C4 SA 3
EF-1 F0ewa#D FLOW TEST WITN PUMP 525e E E W ER SE Flow *ES T WITM Puge 52A.
v i-6 a 3
F.11 to FK SA 1
EF-1 F0ewA40 FLOW TEST u!TM PUMP 52A, REVERSE FLOW TE9T WITM Pu1P 528.
APwen! fos H.H.
4 Sr WIT H, CHIFF E9Cf 4EEP OATEt 13/26pyg eAGE 35
%Ip S
ps;. _ -
w_
=yw 5 gy;=Ng g ggy --
7 c,- = m -
- I n
T4911 38 V4L Q1 FOR leIICH RELIEF 13 GEtelG REGUESif0 stEV osse ooo e m ee eee e e e e e ee e e e ee e e e e e e e e ee ee e e e e e eee e e e e ee e ee e eeee eeee eee eeeeee ee eee e e ee eeee e e eee e e e eee e e e eee e o
eeeeeeeeeeeeeeeee o SVstems Stevice e r*ERGFNCV SERV!CE Wie.
e a
ISO see.e JCP-1942F '
ofstEt CREEst UNIT 1 e agraa#FD 8tY H. LL0v4 DaTE 05/81/74 e
e REVIEIIES eve N. MOLLAste SATE: 86/0F#Fe coseeeee e eeeee e............ s o s o e e ee eee e eee ee ee ee eeee ee ee eee eeee eee eeee ee ee eeee eee eeeee eeee e o
o e
v4Lvt REASON FOR TESTI NG
- e WALVF Mu*lE9
- CLASS C00*D CATEG097 SIZE v4LVE ACT.
8804 p.
TEST TES T REQUESTING to GE TNATE A9CDE IInt TfPE P 05.
DutteeG seETM00 EXEMPf!Oel PEftFOR esEO
- eocoece s e e............ee ee ee ee e m o eee eee ees s ee eeee eeee ee e eeee eee eeee eee..T fPE
...eeee eee e..........
eee eee eee ee ee eee eeeeee ee e e eee ee e e eeee.
03-07 3
8-13 E
14 SF 00 0 0
EF-1 E-1 se0TE 1 EF-2 ET-2 E-1 Ef=2 v3-04 3
C=14 E
in SF 80 0 0
EF-1 E-1 NOTE 1 EF-2 Ef=2 E-1 EF-2 l
l I
l a **e o vF C s H. H.
askwtTwo CH!r F F4GINFfe natte 10/ 26 / F 9 PAGE 36 kh.; M
^ '~
p, 1,
T49LE 348 cosocosenesessesseeeeessee osoesseeesseeesseeeeeeeees CLARIFICAf t0N OF REQUEST FOR RtL..I.EF..eeeeee................EV. Z.e...S w ierF9 R
o
.ooe eeeeeeeeeeeeeeeeeeeeeeeeee e
SYSTE**
SE*W T E o EWERGENCY Stef!CE WTR.
e e
ISO N0es JC P-1942 F OTSTER CREEKe UNIT 1
- PDEPA*FO 9ft H. Llov0 OATTI 05/01tF4 o
e REVIEWEO 978 N. NOLLANS DATE k '-
coseeeeee ee e eeee e e e eeee...so oooo esesose eeee eo sose eeee eeeeeee eeeooss eseose sese.oe e
e e
e e ee ee eee e s e
NOTE VALWF N'JM S E D e
o REMA443 e
e o
oeoe osos s e s e o s e o o o ooo s e e eeoo o o o o o oo o o s e e e e e e e ee ee eos o e o o s eee e
o,seees i
V3-47 FA TLURE OF THIS VALVE IN THE CLOSE0 POSITION WOULO CAUSE A LOSS OF COOLING WATER V3-9A FLOW r804 THE CONTA!0 STENT SPRAY HEAT EXCHANGERS TO THC SERWICE WATER DISCH ARGE HF. ADED l
l l
l l
l ADP20VfCs H.H.
A$rWITH, CH!?F ENGIN1.f # n4TEt 10/?4/74 PAGE 37 e.
m e, cus -
.u
- c-
- ^
Es
~
l
.p ;.
3 4
TA3LF 18 VALVES 4EINS TESTES I e eee ee e e e ee e ee e e e e e ee e e e e e e e e e e e s s e e o o o o o o o o o o o o e se e ee e eeee e ee e.N. 4 0608 04 000.E W
't R
06/18/79 L
- S W1T89 : CLPSEO COOLING W4TED e
1 e
ISD N0.8 19928 OYSTER CREEKe UNIT 1 l
- PCEp4Rr0 9Y H.
LLOYD SATES 84/2A/74 e
e REVIEWE0 SYs M. HOLLANO DATES 06/87/T8 l
- seee eeo s e.................... e e eee e ee e e ee e eeee ee e eee ee e eeee eee e e ee esseee e e eee e e ee e e
e WALVE
- VALTE NuME 9
- CLASS C004D C4TEGORY SITE VALVE ACT.
NORM.
TEST TEST INATF A f [NI TVP RENARK$
e eeeeeee ee ee e ee e e ee eee ee.ooes...........R0 0 E..................E.... T Y P E... PO..S.e... O UR t h G... N E..T l
v5-156 3
F-5 X
12 CK SA 3
EF-1 REWERSE FLOW TEST NOT REQUIRED IF SOTH
=
COOLIMG W ATER PUMPS ARE OPER ATING.
v 5-15 3 1
E-5 E
12 CK SA 3
EF-1 REVERSE FLON TEST ss0T REQUIRED IF 80TH COOLING WATER PusePS ARE OPER ATING.
app *0VEOs H.H.
40(WIT H, CHIT F ENGIN{Eo DATE:
10/ 2e / F 9
- AGE 38
Ta te va IS 9EING R REV. 2 06/18# T 9
...........................................m.L.F.......t.vF s..F04 WN IC.M REL.I E.F............E Q UE. S TF 0...............................
I
- SYSirNt CLOSE3 CCOLING W4TED ISO NO.8 19428 OVSTER CREEW, UNIT 1
- PEEPA.E0 978 H.
LLOYO DAfit 04#28/F#
AEVIEWED BYt N. HOLLAND DATE8 06/9F#F 8 e
i WALVE l
- VALVE Nu14r.
- CLASS C0080 CAffG04f
$!!E VALyt ACT.
NORN.
TEST TEST REQUESTING TO BE REASON FOR TESTI NG
- th4TE A
t t h)
TVP
........................................... 8 C 0 E......................E...... T Y P E.... P O.S.
... O UR ING.........E.T N0 0.......E. ME.MP T I ON.........
N v5-169 2
G-13 M
CE SA EF-1 E-5 NOTE 2 EF-3 V5-1*7 2
G-11 W
6 GA M0 O
EF-1 E-5 NOTE 1 EF-3 l
ET-2 E-5 ET-2 f5-166 2
F-13 r
6 GA M0 O
EF-1 E-5 NOTE 1 EF-3 ET-2 E-5 ET-2 1
EF-4 v5-167 2
F-15 4
6 GA M0 O
EF-1 E*5 NOTE 1 EF-3 ET-2 E-5 ET-2 V5-136 3
0-4 E
12 SF M
0 EF-1 E-7 NOTE 3 N OME l
s pro o vE o s H.H.
aswWITH. C4!?F F4GitEE8 SaTEt 10/?6/F4
. AGE 39
_3.,
l.
oe.. e e e................................. T A 4L E. 3 A 8 C
...L ARIFICA TION OF RE0utST FOR RELIEF....
.ee ooooosese.ooeeeeeeeeeeeeees........
..REv. 2 06/18/79 e
................eee
- SYSTTwt CLoiEO COOLING WA TE8 o
ISO NO.8 19624 OYSTEP CREEK. UNIT 1 i
- PCEpaeEn 978
- 4. LL9?D GATFS G4/29#T4 e
e REVIEWE0 SYs N. HOLLANO DATES 86/0F/T4 e.eee...e.e...........ee...............
...................e.................................................
..............o e
N0'E VALVF NH1*E*
e R ENARES l
I j
1 VS-167 CLOSING THIS VALWE WILL CAUSE LOSS OF CCOLTIIG WAFE8 TO THE RECIRC PUMPS AND WOULD DESTROY THE SEALS.
V5-166 v5-167 l
l 2
V5-165 WALVE C Alpe07 SE REVERSE Flow TESTED DURING NORMCL OPERATION. FLOW l
TO RECIRC POM*S CAtt ONLY 9E SECutEO OJ4tNG REFUELING.
1 3
V5-L36 THIS 15 A MANUAL FLOW CONTROL VALVE USEO TO REGUL ATE Flow THROUGH THE RSCCW HEAT ENCMANGEes.
l l
l l
l l
1 A *P* 0V F n t H.H.
SS W ITH. CHI 8 F EEGTEEE* 9ATEs tort /'s PAGE 63
=-
T
..................................A9LF it.........V ALWfs 4E..I NG TE.STE..D IN..A CC.04 94NC.E..W.I.TH C. ODE..RE.
- 2.. 86/18/F9 R
- FvSfrMt FIRE #40TFCT10N ISO 40.8 JCP-19425 OTSTER CREEK, UNIT 1
- PCEPA**O 8Y
- 4. LLOYD DATES 85#02/F8 REWEEWE0 SV8 N. MO DATE: 06#86/T4
.................................................................................................... LLANO VALVE
- VALWE NU19F R
- CLASS C0090 CATEGORY S!?E WALVE ACT.
NetM.
TEST TEST o
REM ARES
...............................INATE..A......D..E...IM)......E.....TYP E...POS.......... RING.......tTHOD.*..........................
9C 4
TYP OU se
..es==.
v9-2 3
C-3 4
EF-1 FORUMB FLOW TEST WITM PUMP 1-2, REVERSE FLOW TEST WITH PU4P 1-1.
Vt-3 1
0-4 4
SK SA 3
EF-1 FORWARO FLOW TEST WITH THE P040 Pune, i
REWERSE FLOW TEST WITM PUseP 1-2.
V9-19 1
E-4 E
3 14 SA 3
EF-1 F04WA40 FL0ef TEST WITH THE JOCKEY PUNP, REWERSE FLOW TEST WITM PUNP 1-1.
V9*1 3
EF-1 F0ftWMD FLOW TEST WITH Puser 1-te REVERSE FLOW TEST WITH PUMP 1-2.
v9-12 3
E-6 X
GA 4
0 1
PW-1 V9-7 3
E-6 X
12 GA 4
0 1
PW-1 W9-28 3
C-T E
4 GA N
O 1
PW-1 U9-A 1
C-6 X
12 GA M
0 1
PV-1 V20-93 3
C-9 X
6 GA M
C 3
EF-1 v20-99 1
0-9 E
EF=1 v11-46 3
0-11 4
CA 4
C 3
EF-1 v11-65 1
0-10 X
4 GA M
C 3
EF-1 v4-33 3
E-11 X
12 GA N
O 1
PV-1
- 2C-92 3
F-10 x
6 CA 4
C 3
EF-1 APPPOVEQt H.H.
A S( W IT H. CHIU FNGINEE 9 DATFS 10/ 24 # T S SAGE 41
,,,,,. ; y.
~~
m
-~
y v~ n er w;;(qm3 yty?~Kw'*% W
'L
^~
esseeee..
......................TA9L.E..18 VALVES 9fte eeeeeeeeeeeee.eG TESTED IN ACCORDAseCE NITH C00C REGUIREseENTS j
REv 2.
8 6/18/ F 9 e e eeeeeee eeee eeeeee ee eee e e ee e eee e e eee e ee ee eee e eeee e e e eee e ee ee.
e eeeeeeeeeeeoosee
- SYSTE4 FIAE **0TECTIGN e
ISO se0.s JCP-19425 Of STER CREEK. UNII 1 e cotongEO ev t H. LLotD SAf te 95/03/F8 e
e 4EvMisEO 878 N. HOLLANO 46/ 06#T 4
.eeeeee.....................................................
ee.eee....... eeee.ee
.ee.e................ DATES e
e e
v4LVE r
e VALVE seUN4E t
- CLAS1 C0040 CATEGORT SIFF WAL yt AC T.
IIORN.
TEST TEST e
e AB
(
TVP RENARItS ee ee ee e.......................T N A TF..........C D E.........INI.....E..... TYPE.. 805......O. UR..I NG...NE.T.H0 0 t
l
...eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee...e U2e-se 3
E-13 x
6 CK SA 3
EF-1 l
v9-1 e 3
12 CA el 0
1 P V-1 09-13 5
F-6 y
12 GA N
O 1
PW-1
+
AmeP0tF 91 H.H.
A S *CW Ti ed. CHisr ENGitEE' nATE8 10/ 24/ T S PAGE 42
TA9tE 18 VALVES 9F eeeeeeeee eeees se............ooes see eee e e eeeee.o e ooeIf8G TESTES IN ACCOR OA NCE MI TH C. ODE..RE..SIIREMENTS REV. 2.
86/10/79 ee oo....... e eeeeeeeee.o......
e
.....oe eeeeee.eeo,eoeeeeeeeeeeeeeeeee..
SYST**t
- A0 WASTE T*FATNENT e
150 NO.8 JCP-19426 OYSTER CREEK UNIT 1
- PSFP A*EO 97 8
- 1. LLOYO DATES 45#82/78 e
REVIEt4E0 SV8 N. HOLLAtte DAT 86/86#78 o
e esee eee. e e o e e e e e e e s oo e ee s s e e e e ee e e e e e o s...e e e e..........o o oos e...............eeee eeee.....e.................E 8
o VALVE
............ee
- WALVE NU49f *
- CLAS'; C00e0 CATFG0tf SIZE WALVE ACT.
leetM.
TEST TEST e
e TNAfr A 9CDE IINI TYPE TYPE POS DURING 8eETN00
- aE4 ARKS eses eee e e ee e ee e e e s ese e ss e sse eee e e ee e ee s s o oo oe se ee esoo ose oooo seee e V 22-1
?
J-8 X
2 CA A
0 3
EF-1 j
3 EF-5 3
ET-2 V22-2 2
J-9 Y
Z GA A
0 3
EF-1 i
l 3
EF-5 l
3 ET-2 l.
W22-29 2
J-8 X
2 GA A
0 3
EF-1 l
3 EF-5 3
ET-2 V22-29 2
J-8 X
2 GA A
0 3
EF.1
]
3 EF-5 3
ET-2 a
a pps 0VE D s H.H. AttWITH. CHlir EmCYNEE' 9ATEe 1*/24/79
- AGE 63 vl n ~ ei n %s-
>w-u.
3;
.~s.
.s.
~.
-.= s
.s.
uw.
w w 5.
~
3 u
W
. =
<.f l'
s
=
g.
a
. ~ z
=.
.t it l
w a.t B
.5.
W e
=f.
w.
uS w-.
c m.
z s
,e w
w.
E l
=
8 M
v.
r..
5 v.
32 u
v
.m..
.w at
.t. SCS
- w W
ww
.s.
.f
= ;
W w
. ~.. =.
... ~
w
.. r
.a w
w.
....o w o s
.s ou
.e
. w
.s w.
u..
s.
e.
=
e..
ow.
w...
o.
oo.z.
.r
.. ~
1u
.o a.
s.
6
. s.
~ o.
- s.....
.z ~
r s a.
s
=-
u r v
z u
w.
F 2.
e..
o
.e ze
=
a-
.e.
.~
e
}.
.E.F.
.s w
er 6
9 i
l w
i
)
a.
- fwW:
i
~..
.E
- s
.s
~
s
=
.s...
w.
=
3 w.
w w
~
5.
.5
=
w W
=.
E w
ow..
.=.
=
..w.
ss e o.
,
=.
l 4
W i
o.
o.
953 25:
l 5
3.
we t
5
.=
1
=.
a r
w i
=
.u. A g
m.
=
w a.
W
.c I
I
.w c
.z
.s a.
w t
=
r,.
-1 t
. ~.,.
t:
i t
l
.s w
i wEa r
..o
.s.
-a s
e u.
i e.
o.
.r o>z
.~.
. o.
.v.
=
a
,v.,
a, e
u w
~
e.
. - a w r
~
r i.
E o e o
=
ze A,
s o,
te t
g ty 7.L
I l
49ee.Oee4e.e e.
98 4.
.S
=.
G.
=.
v.
2 e 3
==.
G.
O 9
M 2
Ge#
a.
O tai ta.f
.J N
Y an.
U.
O sep D.
W M.
te,.
Lad W@
N em tal 3 M
Dge tad.
O O3
.,s Saa g
.8 O
- O, e.,
2
=
e,
\\
M
.n.
m.
. o.
w.
.t 953 a t,h.
w.
e W w
i w
a.
s
\\
5 I
x w
1 6
2 3
)
s
-+
a
,M
,f 1
.s i,.
w x.
w
.W
=
e
.z. E 5
., 5
~
a 3:
.C. 8 3X w
a s.,
s u
a.s.
s
~.
. as
.a,
n a.
+
w.
m, r
.W w
m..
er w
.s
.is...
.r e.,
a.
i.
=
=
~
2.-
e o.
u
. s, o
.~.
~
z~
.s
-=
x
=-
a
.r e a
- r..
.c.
1a
\\
=.
s o,
a.
4 t-
>w om gC t
I
. la, 5.i
APPENDIX 2D NRC STAFF GUIDANCE FOR PREPARING PUMP AND VALVE TESTING PROGRAM DESCRIPTIONS AND ASSOCIATED RELIEF REQUESTS PURSUANT T010 CFR 50.55a(g)
The guidance provided in this enclosure is intended to illustrate the type and extent of information that should be provided in proposed pump and valve testing program descriptions and to support associated requests for relief from ASME Code requirements. By utilizing these guidelines, ifcensees can significantly reduce the need for having to respond to additional information requests from the NRC staff.
I.
Pump and Valve Testing Program Description A.
Scope of the Program:
1.
The pump testing program should include all safety related*
Class 1, 2 and 3 pumps that are provided with an emergency power source.
2.
The valve testing program should be limited to the safety related* valves. All such valves must be addressed in the program and should include, as a minimum, those in the following systems. Valves in these systems which are used for operating convenience on1.y - such as manual vent, drain, instret and +ast <alves, and valves used for maintenance only should be excluded.
For PWR's:
a.
High Pressure Injection System b.
Low Pressure Injection System c.
Accumulator Systems d.
Containment Spray System e.
Primary and Secondary System Safety and Relief Valves t
f.
Auxiliary Feedwater Systems
- Safety related are those pumps and valves necessary to safely shut f
down the plant or mitigate the consequences of an accident.
=J
~_
2 g.
Reactor Building Cooling System h.
Active Components in Service Water and Instrument Air Systems which are required to support safety system functions 1.
Containment Isolation Valves that are required to change position on a containment isolation signal
- j. Chemical and Volume Control System k.
Other key valves in Auxiliary Systems which are I
required to operate to directly support plant l
shutdown or safety system function; such as, emergency diesel starting air valves, component cooling water supplies, etc.
l.
Residual Heat Removal System I
m.
Reactor Coolant System For BWR's:
a.
High Pressure Coolant Injection System b.
Low Pressure Coolant Injection System c.
Residual Heat Removal System (Shutdown Cooling System)
I, d.
Emergency Condenser System (Isolation Condenser System)
I e.
Low Pressure Core Spray System j
f.
Containment Spray System g.
Safety, Relief, and Safety / Relief Valves h.
RCIC (Reactor Core Isolation Cooling) Systen.
- i. Containment Cooling S.i stem
- j. Containment isolation valves that are required to change position on a containment isolation signal 2D-2
k.
Standby liquid control system (Boron System) 1.
Automatic Depressurization System (any pilot or. control valves, associated hydraulic or pneumatic systems, etc. )
Control Rod Drive Hydraulic System (" Scram" function) n.
n.
Other key valves in Auxiliary Systems which are required to operate to directly support plant shutdown or safety system function; such as, emergency diesel starting air valves, component cooling water supplies, etc.
o.
The following information should be provided for NRC staff review i
of the Pump and Valve Testing Programs-1.
Three sets of P&ID's, that are large and clear enough to be read easily, and which include all of the systems listed above, with the ASME code class and system boundaries clearly marked. The drawings should include all of the components present at the time of submittal and a legend of the P&ID symbols.
l.
2.
Identification of the applicable ASME Code Section XI Edition and Addenda.
3.
The period for which the program is applicable.
4.
Identification of the component ASME Section III Code Class.
5.
For Pump testing, identification of:
a.
Each pump required to be tested (name and number) b.
The tast parameters to be measured c.
The test frequency k
l l
m
6.
For valve testing, identification of:
a.
Each valve in ASME'Section XI Categories A and B that will be exercised every three months during normal plant operation (indicate whether partial or full stroke exercise, and for power operated valves list the limiting value for stroke time).
b.
Each valve in ASME Section XI Category A that will be leak tested during refueling outages (indicate the leak test procedure you intend to use).
c.
Each valve in ASME Section XI Categories C and D that will be tested, the type of test and the test frequency. For check valves, identify those that will be exercised every 3 months and those that will only be exercised during cold shutdown or refueling 1
I outages.
d.
Each valve in ASME Section XI Category E that will be operationally checked.
e.
The following additional information, if practical:
1.
The valve location coordinates or other appropriate location infonnation which will expedite locating the valves on the P& ids.
ii.
Identification of all valves that are provided with an interlock to other components and a brief description of that function.
II.
Requests for Relief from Certain Pump or Valve Testing Requirements It has been the staff's experience that many requests for relief from testing requirements, submitted by licensees, have not been supported by adequate descriptive and detailed technical information.
This detailed information is necessary to document why the burden imposed on the licensee in complying with the code requirements is not justified by the increased level of safety obtained from the testing.
Relief requests which are submitted with a just.fication such as
" impractical", " inaccessible", or any other categorical basis, require additional information to allow the staff to make an evaluation of that relief request. The intention of the guidance 2D-4
. set forth below is to illustrate the extent of the infonnation that is required by the NRC staff to make a proper evaluation and to adequately document the basis for granting the relief in the safety evaluation report. The NRC staff believes that if this infonnation is provided in the licensee's submittal, subsequent requests for additional infonnation and delays in completing the review, and granting the relief, can be considerably reduced.
A.
Specific infonnation required for NRC review of requests for relief from testing requirements:
1.
Identification of the component for which relief is requested:
a.
Name and number as given in FSAR b.
Function c.
ASME Section III Code Class d.
For valve testing, also specify the ASME Section XI valve category as defined in IW-2000 2.
Specific identification of the ASME Code requirement that has been determined to be impractical for each component.
3.
Information to support the determination that the requirement in (2) is impractical; i.e., state and explain the basis for requesting relief.
4.
Specification of the inservice testing that will be performed in lieu of the ASME Code Section XI requirements, if any.
5.
The schedule for implementation of the procedure (s) in (4).
B.
Examples to illustrate several possible areas where relief may be granted and the type and extent of information necessary to support the granting of relief:
1.
"Accessibil i ty":
The regulation allows relief to be granted from code requirements because of insufficient access provisions.
However, a detailed discussion of actual physical arrange-ment of the component in question to illustrate the p
insufficiency of space for conducting the required test i
is necessary.
(
k 2D-5
1 l
. In addition, discussion of the alternative surveillance techniques that have been considered should be provided.
If these alternative techniques have been detemined to be iupractical, the basis for this detemination should be provided.
2.
"EnvironmentalConditionsProhibitive"(e.g.,highradiation level, high temperature, high humidity, etc.):
Although it is prudent to maintain occupation radiation exposure for inspection personnel as low as practicable, the request for relief from code requirements cannot be granted solely on the basis of high radiation levels.
I A balanced judgment between the hardships.and compensating increase in the level of safety must be explicitly justified.
y Therefore, detailed information regarding the radiation levels at the required test location, along with estimated yearly man-rem exposures associated with the testing, should be provided. Alternative testing techniques that have been considered should be discussed.
If these alternative T
techniques have been determined to be impractical, the basis for this detemination should be provided.
3.
" Instrumentation Not Originally Provided":
h; Q
Information to justify that installation of the needed y
instrumentation to comply with the code requirements would p;
. result in undue burden or hardships without a compensating M
increase in the level of plant safety should be provided.
E Alternative testing techniques that have been considered 1-should be discussed.
If these alternative techniques e
have been detemined to be impractical, the basis for this detemination should be provided.
4.
" Valve Cycling During Plant Operation Could Put the Plant in an Unsafe Condition":
A detailed explanation as to why exercising tests d; ring plant operation could jeopardize the plant safety. Examples j
of the type of valve that the staff considers to be in this category are: valves whose failure in a non-conservative position during the cycling test would cause a loss of total system function; valves whose failure to close during the I
2D-6 u
s_i ^ -
l
-7_
cycling test would cause a loss of containment integrity; and valves, which when cycled, could subject a system to pressures in excess of their design pressures. A plant specific explanation must be provided.
5.
" Valve Testing at Cold Shutdown or Refueling Intervals in lieu of the 3 Month Required Interval":
The licensee should explain in detail why each valve cannot be exercised during nomal operation. Also, for the valves where a refueling interval is indicated, the licensee should explain in detail why each valve cannot be exercised during each cold shutdown.
C.
The following acceptance criteria for granting relief are utilized by the staff:
The licensee must successfully demonstrate with documented infonnation that:
1.
Compliance with the code requirements would result in hardships or unusual difficulties without a compensating increase in the level of safety, and noncompliance will provide an acceptable level of quality and safety, or i
2.
Proposed alternatives to the code requirements or portions thereof will provide an acceptable level of quality and sa fety.
III. Standard Fonnat for Valve Testing Submittals A reconsnended standard format, for the valve portion of the pump r
and valve testing program and relief requests, is included as an attachment to this Guidance.
The NRC staff believes that the use of this standard format would reduce the time spent by both the staff in its review, and by the licensee in their preparation, of the pump and valve testing program submittals. The standard fonnat includes examples of relief requests which are intended to illustrate the application of the standard fomat only and are not necessarily applicable to any specific plant.
i n
2D-7 J-
n, a
am a_
- - - - ~ - - -
N ATTACHMENT i
i RECOW4 ENDED STANDARD FORMT FOR VALVE INSERVICE TESTING PROGRAM SUBMITTALS J
I J
l 2D-8
l lIl 1 '
,l
- I i
=
)s isa E
b GA f
P e
i i
m r
o Sf A
K 2
Rd Ae E
Ms Eu 5
R e
e 4
e m
m 0
b i
i 1
t t
o t
e e
k k
O t
o o
o r
r N
N t
t D
(
s s
I P
c c
e e
s s
0 0
6 3
G i
N I
S T
EDg k = ge C
E LOO h'
C a"
g;g X
X X
T
,i
,(
V V V V N
E T T V V V T R R R i rT N
Dgg5*2 gg E O C C C Q M S S. S S Qo M 0P M
O O
8Uh -lg L C -
- C
_ C C
A A A A A A A A 0 M
g*%;3g M N S S S M S S S S M E
TS L-L L L L A E K K E L E E E E A Y
K# I,g G O C C R G R R R R G S
T 4 4 N
6 6
/ /
0 A
O54 gg 4 6 1 1 3 4 3 3 3 3 1 LO0 t.
X X
C Y
D 1
R f
A er I
vo C
X X X X X X X L
l g I
ae X
Vt B
X U
a A
C A X
E i
i
'4 5 5 5 4 1
1 1
0 0 4 1 1 1 1 1 1 1
1 1 1 1
A N
beg 0 0 C C E 0 8 8 A 8 0 M
I l
.3 G 3 3 3 3 3 3 3 3 2 2 2 S
Y S
r ee C
8 C 8
vb 0 0 7 2 7 4 2 2 5 9 4 l m 1
0 1
0 0 3 2 2 1
2 4 au 7 7 7 7 7 8 7 7 7 7 7 s
VN u?w p
,~
l lil Ll,l ll l
i 1ll
LEGEND FOR VALVE TESTING EXAMPLE FORMAT Q
- Exercise valve (full stroke) for operability every (3) months LT - Valves are leak tested per Section XI Article IW-3420 MT - Stroke time measurements are taken and compared to the stroke time limiting value per Section XI Article IW 3410 CV - Exercise check valves to the position required to fulfill their function every (3) months SRV - Safety and relief valves are tested per Section XI Article IW-3510 DT - Test category D valves per Section XI Article IW-3600 ET - Verify and record valve position before operations are performed and after operations are completed, and verify that valve is locked or sealed.
CS - Exercise valve for operability every cold shutdown RR - Exercise valve for operabi.11ty every reactor refueling
\\
e t
'I 2D-10
RELIEF REQUEST BASIS System: Auxiliary Coolant System. Component Cooling 1.
Valve:
717 Category:
C Class:
3 Function:
Prevent backflow from the reactor coolant pump cooling coils Test Requirement:
Exercise valve for operability every three months Basis for relief:
To test this valve would require interruption of cooling water to th'e reactor coolant pumps motor cooling coils. This action could result in damage to the reactor coolant pumps and thus place the plant in an unsafe mode of operation.
Alternate Testing:
This valve will be exercised for operability during cold shutdowns 2.
Valve:
834 Category:
B-E Class:
3 Function:
Isolate the primary water from the component cooling surge tank during plant operation.
It is normally in the closed position, but i
routine operation of this valve will occur j
during refueling and cold shutdowns.
f Test Requirement:
Exercise valve (full stroke) for operability every three (3) months.
?
Basis for Relief:
This valve is not required to change position during plant operation to accomplish its safety function.
Exercising this valve will increase the possibility of surge tank line contamination.
.j Alternate Testing:
Verify and record valve position before and af ter each valve operation.
r i
ci l.
2D-11 s
r
. 3.
Valve:
744B Category:
A Class:
2 Fur.:+..on:
Isolate the residual heat exchangers from the cold leg R.C.S. backflow and accumulator backflow.
Test Requirements: Seat leakage test Bases for relief:
This valve is located in a high radiation field of ar/hr which would make the required seat leakage test hazardous to test personnel. The estimated yearly man-rem exposure associated with perfoming the required seat leakage test is We intend to seat leak test two other valves (8758 and 8668) which are in series with this valve and which also prevent backflow. We feel that by complying the seat leakage requirements for 7448 we will not achieve a compensatory increase in the level of safety.
Alternate Testing: No alternative seat leak testing is proposed for 7448.
j m
SECTION 3.
WELD AND SUPPORT INSPECTION PROGRAM OYSTER CREEK NUCLEAR GENERATING STATION TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS 3-1
3.0 INTRODUCTION
3-1 3.1 Program Update Description.
3-2 3.2 Technical Approach.
3-3 3.3 Key Technical Points..
3-4 3.3.1 Code Exemptions.
3-4 3.3.2 Alternate Examinations for Exempt Components 3-4 l
3.3.3 Relief Requests.
3-4 3.3.4 "In Lieu Of" Examinations.
3-5 3.3.5 Containment Penetrations 3-5 3.3.6 Pressure Tests 3-5 3.3.7 Augmented Systems and Components 3-8 3.3.8 Class 3 Systems and Components 3-8 Appendices 3A EXAMINATION
SUMMARY
FOR ASME CLASS 1 SYSTEMS AND COMPONENTS.
3A-1 3B EXAMINATION
SUMMARY
FOR ASME CLASS 2 SYSTEMS AND COMPONENTS.
3B-1 l
l 3C INSERVICE INSPECTION WELD
SUMMARY
SHEETS 3C-1 I
3-1
SECTION 3.
WELD AND SUPPORT INSPECTION PROGRAM OYSTER CREEK NUCLEAR GENERATING STATION 3.0 Introduction In the past, there have been divergent opinions on the requirements for Inservice Inspection of nuclear power plant components.
As specified in 10 CFR 50, the current Code in effect is the 1974 Edition of the ASME Boiler and Pressure Vessel Code,Section XI through the Summer 1975 Addenda (hereinafter referred to as the " Code").
There is a general consensus that the Edition of the Code accepted by the Nuclear Regulatory Com-mission (NRC) provides a reasonable level of inspection that will help to ensure the pressure boundary integrity of essential systems of a boiling water reactor plant such as Oyster Creek.
However, there are areas needing further refinement.
For example, the Code permits systems that perform an emergency core cooling function to be totally exempted from examination provided the control of chemistry of the contained fluid is verified by periodic sampling and test; whereas it requires volumetric examination of many fillet welds that are not inspectable by that ezmnination method.
Further, since the adoption of the 1975 Addenda, the ASME Section XI has issued new requirements in its later Editions and Addenda while the NRC
]
l has released several guideline letters relating to inservice inspection.
These new Code requirements will also have impact on future updated inservice inspection programs for the Oyster Creek Plant.
Therefore, these requirements were considered along with the NRC guideline letters in developing this Program.
Thus, a viable alternative has been developed which meets the purpose and intent of doing the Inservice Inspection while it helps to ensure the integrity of all essential pressure boundary and safety classified systems.
4
This Report identifies the Inservice Inspection weld examination and component inspection program for the Oyster Creek Nuclear Generating Station for the fourth 40-month opera-ting period; i.e.,
the first three and one-third year period during the plant's second ten-year inspection interval.
The technical bases for any deviations from the Code are also l
identified.
In accordance with the current requirements of 10 CFR 50, this I,nservice Inspection Program will be applicable for a 40-month period ending April 8, 1983.
Subsequent review and update will be in accordance with the 10 CFR 50 requirements in effect at that time.
3.1 Program Update Description The Weld and Support Inspection Program for the Oyster j
Creek Nuclear Generating Station is presented in the Appendices to this section of the Report.
These Appendices are:
3A - Examination Summary for ASME Class 1 Systems e
and Components 3B - Examination Summary for ASME Class 2 Systems e
and Components e
3C - Piping Weld and Support Inspection Program e
In addition, Inservice Diagrams, color-coded to indicate ASME Code Class 1, 2 and 3 boundaries, are forwarded with this Report to assist in its review.
To facilitate review, Appendices 3A and 3B are presented in a format consistent with that of Tables IWB-2600 and IWC-2600, respectively, of the Code.
These summaries provide the Item Number, Examination Category, and Areas to be Inspected from the Code, as well as the Inspection Method (s) and Extent of the 3-2
Examination to be Performed.
Remarks and notes are included, where appropriate, to provide amplifying information or to request relief from specific Code requirements.
Appendix 3C is referenced in the cases where the Inspection Method (s) and Extent of the Examination to be Performed are presented in the Piping Weld and Support Inspection Program.
Appendix 3C and the color-coded Inservice Diagrams enclosed with this Report contain all the information required to perform the review of the Piping Weld and Support Inspection Program.
This includes:
Code Exemptions and Relief Requests used to develop this program; an explanation of Weld Summary Sheet terms; a Weld Summary Sheet Index and a Cross-Reference to Inservice Diagram Numbers; and the Weld Summary Sheets, including an expla-nation of the amplifying notes.
3.2 Technical Approach l
In general, the inservice inspection requirements in the H
1974 Edition through the Summer 1975 Addenda which are applicable to ASME Class 1 components and systems are considered to be suf-ficient and workable to provide a reasonable and prudent level of inspection that will help to ensure the pressure boundary integrity of essential systems of a boiling water reactor plant.
However, the Code requirements applicable to ASME Class 2 com-ponents and systems are considered in many cases to need enhance-ment.
The ASME has recognized various aspects that need improve-ment in the 1974 Edition through the Summer 1975 Addenda and has subsequently made many improvements in its later Editions and Addenda.
These later Editions and Addenda are not currently recognized by 10 CFR 50, and therefore, are not used directly in the Inservice Inspection Program.
The Inservice Inspection Program Update was prepared to the degree practicable in accordance with the Code requirenients.
3-3
Where the Code requirements were determined to be either incomplete or impracticable, specific requests for relief from Code require-ments are identified.
Each request for relief has been evaluated and an alternative examination is specified.
In almost every case the alternative examination results in a higher level of confidence in system integrity than the original Code requirement (the exceptions to this are welds that are physically inaccessible for examination).
3.3 Key Technical Points 3.3.1 Code Exemptions Exemptions identified in IWB-1220 and IWC-1220 of the Code i
j are used in this Program with the exception of IWC-1220 (c),
I which exempts emergency core cooling systems if the chemistry of their contained fluid is controlled.
3.3.2 Alternate Examinations for Exempt Components In accordance with Category B-P of Table IWB-2500 for Class 1 and IWC-2510 for Class 2, components exempt from volu-metric and surface examination will be visually examined during i
pressure test in accordance with Code requirements.
In Appendix, 3C, such examinations are listed under "In Lieu of Examination,"
where appropriate.
3.3.3 Relief Requests Where Code requirements are determined to be incomplete or impractical, requests for relief are documented and technically justified in the notes and remarks in Appendices 3A and 3D and in Table 3C-2 of Appendix 3C.
l 3-4
3.3.4 "In Lieu of" Examinations Where relief is requested from examination of component, an "in lieu of" examination is specified.
In most cases, the "in lieu of" examination results in a higher level of confidence in system integrity than the original Code requirements.
3.3.5 Containment Penetrations Appendix 3C specifies a surface examination, if the weld is accessible, for all primary containment boundary to piping welds in all steam-or water-containing piping greater than one inch nominal pipe size.
This exceeds the Code requi. unent in some cases, (and is therefore an " augmented" inspection as discussed in 3.3.7) but is considered necessary because of the importance of the integrity of the primary containment boundary.
The containment penetration is considered to extend to the first isolation valve outside containment and the first seismic re-straint past that valve.
The typical containment penetration is constructed such that one circumferential butt weld inside the penetration is completely inaccessible for either surface or volumetric inspec-tion.
This weld is shown in Figure 3-1.
Each of these inacces-nible welds is identified in Appendix 3C and an "in lieu of" examination is specified.
3.3.6 Pressure Tests In the Weld Summary Sheets, three different types of pressure tests are used.
Descriptions of the three types are given in Table 3-1.
The system " Pressure" test identified as the "In Lieu of Test" for Relief Request R4 (Class 2 systems that operate above moderate energy less than one percent of plant operating time) is intended to increase the overall confidence 3-5
f t
5 kNN5
\\q NN
\\\\\\\\\\
\\\\
k-k N
' p.-l:-;
Q
'.......q.
1..
~..
- 0. :?.%i.?.: *- [%s N
.l..,.'.'.'~.:?i-)
~
... v w;.. ::... y q\\
q 5
N
,....:n.,. y., i
.. : :., s s
N s
s q
s N
k
\\
2
.., e : s h
(
. x.., s n s 4
g g\\. U [*y~
.. ;P j*****~~.."
Inaccessible lCircumferential I
\\
s i
IJeld
\\g i
\\
N N
k f
4
\\
\\*
4\\
\\
\\
\\
\\
\\k Figure 3-1.
Typical Drywell Penetration 3-6
in the pressure boundary integrity of those systems or portions of systems using Relief Request R4.
This test method will verify the integrity of 100 percent of the welds every 3 1/3 years rather than a small portion (can typically be as small as 2 per-cent of the welds during the same 31/3 year period) of the welds as required by the Code.
Table 3-1.
Pressure Test Descriotions Weld Summacy Test Name Sheet Symbol Test Description hydrostatic HYD The Code required hydrostatic pressure test performed each interval as specified in Section XI Paragraphs thA-5000, IWB-5000, IWC-5000, and IWD-5000, as applicable. The hydrostatic test pressure shall be based on the Code requirements; however, overprescuri-zation of the most limiting conponent in a system or portion of a system is not permitted.
For example, piping attached to the reactor l
vessel will be tested with the reactor ves-sel rather than to their own test pressure.
Pressure PRS A hydrostat'e pressure test performed on a system or portion of a system as the "In Lieu of Exam" for Relief Request R4.
The test shall be performed every 31/3 years.
For components that are not required to function during reactor operation, the system test pressure shall not be less than 100 per-cent of the pressure developed during the conduct of a periodic system inservice test.
[IWC-5220 (c) ) For the oyster Creek plant, this would include the Class 2 portion of the following systems: Isolation Condenser, Poison, Containment Spray and Core Spray.
Flow FLW A test performed to poi-trons of systems that cannot be hydrostatic pressure tested, such as lines connected to open tanks. The test shall be performed during system operation every 3 1/3 years. The test pressure shall be that pressure attained daring normal system operation.
3-7
Rev. 2 3.3.7 Augmented Systems and Components As discussed in Section 3.3.5 above, augmented inspection i
requirements will be applied to portions of systems that are primary cor.tainment pressure boundaries.
In a similar manner, augmented examination is specified for Main Steam System piping Rev. 2 between the outer containment isolation valves and the Main Steam turbine stop valves.
The acceptance standards, or their equivalent, applicable to the original construction code for that portion of the Main Steam system shall be used for the evaluation of indications.
3.3.8 Class 3 Systems and Components Class 3 systems at the Oyster Creek Nuclear Generating Station are either in continuous operation or maintained in a standby condition at moderate energy (less than 275 psig and 200*F).
Design and operating pressures are less than 275 psig.
These systems were designed and constructed prior to the issuance of the first Edition of ASME Section XI (the 1971 Edition) and, therefore, prior to the first Edition that addressed Class 3 systems and components (the 1974 Edition).
Since the systems were designed and constructed without the current inspection requirements in view, isolation valves that would permit hydrostatic testing to current requirements are not installed.
i An alternative inspection program described below is therefore implemented to ensure the integrity of the pressure boundary of these systems.
This program incorporates features of the 1977 Edition of the Code through the Summer 1978 Addenda for visual inspection of piping systems and supports.
To provide J-8
Rev. 2 additional assurance of system integrity, these inspections will be conducted once per refueling outage, which exceeds the frequency of Code requirements.
The inspection program for Class 3 systems is as follows:
Item Examination Reference Class 3 Piping (not buried)
VT-2 IWA-2212 Class 3 Piping Supports VT-3 IWA-2213 Buried Class 3 Piping Flow Verification IWA-5244(c)
Relief is requested from the system hydrostatic test, required each inspection interval by Table IND-2500-1, based
(
on the inability to conduct hydrostatic tests of Class 3 systems nev. 2 l
and the increased frequency of VT-2 examinations, VT-3 examina-tion and Flow Verification Tests (required once an inspection period by IWD-2500-1).
i 1All references are from the 1977 Edition of ASME Section XI through the Summer 1978 Addenda.
3-9
4 APPENDIX 3A EXAMINATION SID9tARY ASME CLASS 1 SYSTDtS AND COMPONENTS ASMESECTIOyXI EXAMINATION EXAMINATION ITEM NO.
CATEGORY AREAS 10 BE EXAMINED MET 1tODS EXTENT OF IM3PECTIGP.
l<D1 ARKS Reactot Vessel Bl.1 B-A longitudinal and circumferential NOTE 2 NOTE 2 NOTE 1 shell welds in core region NOTE 2 B1.2 B-B Iongitudinal and circumferential Volumetric welds in shell (other than those The examinatier.s shall covur NOTE 1 (1) the upper 6 feet of the of Category 3-A and 3-C) and meridional and circumferential three longitudinal weld = An the reactor vessel's shell seam welds in bottom head and course and (2) at least 10% or closure head (other than those of 3-C) the length of each meridian weld, and 5% of the length of each circumferential wuld in w>
the closure head.
h 81.3 3-C Vessel-to-flange and head-to-Volumetric 100% of the length of these flange circumferential welds welds will be examined from one side during the inspec-Rev. 2 tion interval.
Bl.4 a-D Primary nossle-to-vessel welds &
Volumetric The extent of the exanination NOTE 3 nozzle inside radiused & blended section. The following nozzles of each nozzle shall cover will be subject to inspections 100% of the nozzle-to-vessel weld, including the radiu:ed Rev. 2 T
and blended area. One nozzle l
of each group listed shall be Recirculation Outlet (5)
I a
b Recirculation Inlet (5) examined during the inspection interval. An inapuction of a c Main Steam (2) &
Isolation Condenser (2) given nozzle will not be repeated d Feedwater (4) until all nozzles of that group have been examined once.
e Core Spray (2) and CRD Hydraulic (1)
- c
\\
Table Iws-2500, ASME ao11er and Pressure vessel Code,Section XI,1974 Edition through the Summer 1975 Addenda N
1 i
~
1 i
APPENDIX 3A (Cont.)
ASME SECTION XI EXAMINATION EXMINATION ITEM NO.1 CATECORY1 AREAS M BE EXAMINED 1 METHODS EXTENT OF INSPECTION kEMARKS i
feeactor vessel 51.5 B-E Vessel penetrations, 14.cluding Visual the area surrounding each lene-NUTE 4
{
control rod drive and instru-t stion shall be exar.ined fot i
mentation penetrations evidence of leakage during 1
pressure test, rwamination 2
performed during each inspec-tion interval shall cumula-l tively cover at least 2% of each group of penetrations of comparable size and function.
j al.6 B-F Nossle-to-safe end tselds See Inservice i
Inupection w
Weld summary j
{
Sheets so (Appendix 3C) l
[
Bl.7 -
B-G-1 &
Pressure retaining bolting Vol m tric/
100% of greater than 2 inches in NOTE 5 l
Bl.11 B-G-2 surface /
diameter bolts, studs, nuts, j
Visual bushings, and threads in base j
materials and flange ligaments between threaded stud holes j
I will receive Code specified examinations during the inspec-h,2 tion interval. 100% of the bolts, studs, and nuta 2 inches l
in diameter and smaller will l
be visually examined during the inspection interval, either in place under tension, when 1
the connection is disassembled, i
or when the bolting is removed.
1 f
5 I
Table Iws-2500, ASME Boiler and Pressure vessel Code,Section XI,1974 Edition through the Susumer 1975 Addenda i
I t
T l
l APPENDIX 3A (Cont.)
6 l
ASME SECTION XI EXAMINATION ITEM NO.I CATEGORYI EXAMINATION AREAS TO BE EXAMINED METHODS EXTENT OF INSPECTION HD4 ARKS Reactor Vessel 81.12 B-H Integrally welded vessel supports surface h four 18" stetions of the NOTE 6 reactor vessel to support skirt weld which are accessible will be examined from one side during tM inspection interval.
Bl.13-B-I-1 vessel and closure head cladding None None NOTE 7 B1.14 w
Bl.15-B-N-1 &
Vessel interior, interior Visual h areas shall incituie NOTE 8 Bl.16 B-N-2 attachments, and core support (1) the space above and Rev. 2 0
structures below the reactor core that is made accessible for examination by the removal of congenents during normal refueling outages and (2) attachments and cores support structures walded to the versel wall.
81.17 B-N-3 Bemovable core support struc-Not applica-tures (rwa's only) ble l
B1.18 B-0 Control rod drive housings surface h examinations perfor1eed dur-NOTE 9 Re v.
2 i
(Flange to housing welds) ing the inspection interval shall include 100% of the welds l
in 10% of the peripheral control l
rod drive housings.
i Table IWB-2500, ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition through the Susener 1975 Addenda l
g l
I i
u I
l t
I I
I APPEICIX 3A (cont.)
ASME SECTION XI EXAMINATION EXAMINATION ITD4 No.1 CATECORYI I
AREAS to SE EXAMINED METHOOS EXTENT OF INSPECTION REMARKS Reactor vessel 31.19 S-P Exempted component Visual Class 1 systems will be visu-ally inspected during a hydro-static test in accordance with IWB-5000 at or near the end of the inspectivi interval.
Piping Pressure Boundary 84.1 B-r safe-end to piping welds and See Inser-safe-end in branch piping vice Inspec-welds tion Wald w>
summary 1
Tables (Appendix 3C) 54.2-3-G-1 &
Pressure retaining bolting Volumetric /
100% of greater than ;t Anches in NOTE 5 84.4 B-G-2 Surface /
diarmster bolts, studs, nuts, Visual bushings, and threads in base materials and flange irgaments between threaded stud holes Rev. 2 will receive code specifted examinations during the inspec-tion interval. 100% of the bolts, studs, and nuts 2 inches in diameter and smaller will 4
be visually examined during the inspection interval, either in place under tension, when the connection is disassembled, or when the bolting is re:noved.
E 1
j Table IWs-2500, AsME aoiler and Pressure vessel Code, section XI,1974 Edition through the summer 1975 Addenda u
(
e p
?
l
l APPENDIX 3A (Cont.)
ASME SECTION XI EXAMINATI EXAPtINATION ITEM NO.1 CATEGORY AAEAS TO SE EXAMINED METHODS EXTENT Or INSPECTION REMAK _KS Piping Pressure r
w u.dary 84.5-3-J Circumferential and longitudi-See Inservice B4.9 nal pipe welds: branch pipe Inspectior) Weld connection welds exceeding six Summary Sheets in, diameters branch pipe welds (Appendix 3C) six in. diameter and smallers socket welds B4.9-B-K-1 &
Integrally welded supports and See Inservice 84.10 B-K-2 support components Inspection teeld Susanary Sheets (Appendix 3C) 54.11 3-P Esempt components Visual Class 1 Jystems will be visu-ally inspected during 4 l
hydrostatic test in accor-dance with IWB-SOOO at or near i
y>
the end of inspection interval e*
Pump and Valve Pressure Soundaries 95.1-b5.3s B-G-1 &
Pressure retaining bolting Volumetric /
100% of greater than 2 inches in NCrrE 5 96.1-96.3 3-G-2 surface / Visual diameter bolts, studs, nuts, 9
bushings, and threads in base materials and flange ligaments between threaded stud holes Rev. 2 will receive code specified 1
emaninatione during the inspec-I tion interval. 100% of the bolts, stude, and nute 2 inches in diaster and smaller will be visually exan.ined during j
the inspection interval, either
)
in place under tension, when the connection is disassembled, or when the bolting is removed.
Table Iws-2500, Aanz soiler and Pressure Vessel Code, section XI,1974 soition through the sussner Addenda
- > - = ^ ' " " "
APPENDIX 3A (Cont.)
ASME SECTI] XI EXAMINATIf EXAMINATION g
ITEM NO.
CATECORY AREAS 1D BE EXAMINED METHOOS EXTENT OF INSPECTIot4 IEMAkKS Pusap and Valve Pressure Boundaries e
B5.4-B5.53 B-K-1 &
Integrally welded supports and Surface / Visual 100% of the welded area, on NOTE 10 B6.4-D6.5 B-K-2 support components both sides of the support attachment, and the area extending a distance of two support thicknesses from the welded area alorg the pressure retaining component and alc,ng w
the attactunent, shall be surface examined during the insgection Rev. 2
[
interval.
All areas of the support com-ponents that extend from piping, valve, and pump support attach-monts to and including the attachment to the supporting structure shall be Visual examined during the inspection inte rval.
'the settings of constant and Variable spring-type hangers, snubbers, and shock absorbers i
shall be verified during the inspection interval during the performance of the visual examination.
k s
Table IWB-2500, ASME Boiler and Preseure vessel Code,Section XI,1974 Edition through the Susumer 1975 Addenda FJ
w APPCILIX 3A (Cont.)
ASME SECTI ] XI EXN4INATIf EXAMIt1ATIdN ITEM No.
CATEGORY AREAS % BE EXAMINEL METHODS EXTENT OF INSPECTIOt3 IJJtAF rf, Pump and Va1ve Pressuru Boundaries
')
B5.6 B-L-1 &
Pump cm ang welds and valve
)
tbt applicable. %ere are no Class 1 punp 86.6 B-M-1 body welds casing or valve Q wulda.
i 85.73 B-L-2 &
Pump casings and valve bodies Visual Internal pressuze boundary B6.7 B-M-2 surfaces of at least one pump in each group of g'um1>s Isrf orm-g ing similar functions in the E"V-2 y
system and one valve within each group of valves that ar.:
i I
of tne same constructional design will be examined if
{
they are disas.sembled for any other reason. Wall thickness measurements on all Class 1 i
pumps and valves will be ma.le at least every 3 1/3 years and the data trended in order to a
provide continued assurance of the integrity ot' the prebaute boundary beyond that obtained by the required periodic pressure tests.
B5.8 B6.8 B-P 3
Exempted ccamponents Visual Class 1 systems will be visu-ally inspected during a hydrostatic test in accor-dance with IWB-5000 at or near the end of the inst.ec-tion interval.
{<
re 1
Table IWB-2500, ASME Soiler and Pressure Vessel code, Sectiori XI,1974 Edition through the Sususer 1975 Adden la
~_
APPENDIX 3A NOTES FUTE 1: Reactor suel welds other than those specified are inaccessible because of interference with the bio; ical shield wall.
Request for relief from the Code specified examination is there-fore req ested.
l NOTE 2:
These welds are inaccessible for surface or volumetric examination because of interference with the biological shield wall, various inspections and tests are performed and operational conatraintaa l
strictly observed to assure the integrity of this vessel. Wese include:
Item i<cference (a) Visual examination during pressure test Technical Specification 4.3.C each refueling outage.
(b) visual examination during hydrostatic Section 3 of this submittal test each inspection interval, wy (c) Minimum pressurization temperature Technical Specifications 3.3.A restrictions and associated surveillance and 4.3.A m
program.
l (d) hermal transient restrictions.
Technical Specification 3.3.C (e) Reactor coolant system leakage Technical Specification 3.3.D monitoring.
l Relief from volumetric and surface examination of these welds is therefore requestud.
NOTE 3:
Jersey Central Power and Light previously submitted to the NRC a report justifyinc an alternate inspection program for reactor vessel nozzles based on (1) the excessive amount of radiation exposure required to perform inspections per the Code, (2) stresses for the reactor vessel 25% less than those for a vessel design to the current Code. The Sunurary of this report is attached to this Apt =ndix as Addendum 1 (Page 3A-6).
- o N
l I
1 J
s m _.
APPENDIX 3A NOTES (Cont)
NOTE 4:
he Winter 1977 Addenda and all subsequent Addenda of the Code incorporate, in Article IPA-2210, improved provisions for conducting visual examinations. Pour types of examinations (designated as VT-1, VT-2, VT-3, and VT-4) are identified, each for a specific purpose.
VT-2 is s; ecified to locate "... evidence of leakage from pressure retaining components...".
This subctittal is therefore based on using the VT-2 examination for Category B-E (Pressure-Retaining Partial Penetration Welds in Vessels). This practice is in accordance with the 1977 Edition of ASME Section XI through the Snamar 1978 Addenda, is considered to comply with the pertinent provisions of the l'174 Edition through the Summer 1975 Addenda, and, therefore, no relief is requested.
NOTE 5:
n o Summer 1978 Addenda of the 1977 Code specifies that the Examination Category B-G-1, Pressure Retaining Bolting, applies to bolting larger than 2 in in diameter (Table IWB-2500-1).
Examinatron gy,
Category a-G-2 is defined to apply to bolting 2 in. In diameter and smaller. Relief tu requested, y
therefore, from the pertinent provisions of the 1974 Edition, Susumer 1975 Addenda.
8*
NOTE 6:
In Table IWB-2500-1, " Examination Categories", Summer 1978 Addenda of the Code, Examination Category B-H (Integral Attachments for Vessels), Item No. B8.10 (Reactor Vessel: Integrally Welded
{
Attachments) specifies that examination requirements are defined in Figure Numbers IWB-2500-13, 14,
)
and 15, and the examination method as Volumetric or Surface, as applicable. Figure IWD-2500-13 (Integral Attachment Weld) is representative of the configuration of the Oyster Creek plant reactor vessel, and permits Surface ewamination from the exterior side of the weld. This subcattal is therefore based on using the surface examination for Category B-H (Integrally Welded Attachments, i.e., integrally welded vessel supports). his practice is in accordance with the l'377 Edition of ASME Section XI through the Susumer 1978 Addenda. Relief from the pertinent provisions of the l
1974 Edition through the Sussner 1975 Addenda is therefore requested.
I i
l I
w e+
i I ".
1 APPENDIX 3A NOTES (Cont)
NOTE 7:
Vessel and Closure Head cladding inspection was eliminated in the Summer 1976 Addenda and all subsequent Editions and Addenda of the Code because (1) the cladding is not a pressure retain-ing component and is therefore not within the jurisdiction of the ASME Boiler and Pressure Vessel Code and (2) the vessel Interior examination (ltem No. Bl.15, Examination Category B-N-1) assesses i
the general condition of the vessel cladding. Relief from Examination Category B-I-l is therefore requested.
NOTE 8:
The Winter 1977 Addenda and all subsequent Addenda of the Code incorporate, in Article IWA-2210, improved provisions for conducting visual examinations.
VT-1 is specified for determining
"... the condition of the part, component or surface examined, including such conditions as cracks, wear, corrosion,..."
VT-3 is specified to determine
"...the general mechanical and structural conditions of components and their supports such as the presence of loose I. arts, debris, or abnormal corrosion products..."
Wis submittal is therefore based or. using the VT-3 examination for Category B-N-1 (Interior of Reactor Vessels) and VT-1 for Category B-N-2 kuv. 2 y
3' E
(Integrally-Welded Core Support Structures and Interior Attachments to Reactor Vessels).
This l
practico is in accordance with the 1977 Edition of ASME Section XI through the Summer 1978 O
Addenda, is considered to comply with the pertinent provisions of the 1974 Edition through the Summer 1975 Addenda, and therefore, no relief is requested.
l NOTE 9:
The Winter 1976 Addenda and all subsequent Editions and Addenda of the Code permit either volumetric or surface examination of Category B-0 welds. Surface examination of these welds is therefore specified, and relief from the 1974 Edition / Summer 1975 Addenda requirement for volumetric ewamination is requested.
NOTE 10:
W e Summer 1978 Addenda of the Code specifies that the ewamination method for Category B-K-1 welds (Integral Attachments for Piping, Pumps, and Valves) may be either Volumetric or surface examination (Table IWB-2500-1). The support attachment welds are either fillet or partial wolds and cannot be volumetrically examined. Surface examination of these welds is therefore elected, and relief from the 1974 Edition / Summer 1975 Addenda of Section XI requirement for volumetric examination is requested.
i
?*
N l
Rev. 2 APPENDIX 3A, Addendum 1
SUMMARY
FROM JERSEY CENTRAL POWER AND LIGHT REPORT,
" BASIS FOR INSPECTION SCHEDULE FOR THE OYSTER CREEK NUCLEAR GENERATING STATION REACTOR VESSEL NOZZLES" f
" Summary "This report has presented a conservative estimation of the man-rem required in order to prepare the nozzles at the Oyster Creek Nuclear Generating Station for an inservice inspection that would f
meet the requirements of the present day Code.
The estimation is
]
based on the experience gained in the preparation of the feedwater nozzles for a special inspection in the 1975/1976 refueling outage.
The report shows that a minimum of 862 man-rem would be necessary for preparation of the nozzles.
This corresponds to the allowed L
quarterly dose for 431 men under existing Oyster Creek Station exposure criteria.
k L
L "This report also compares the peak stresses in the Oyster Creek
[
vessel nozzles to the peak stresses in a nozzle of a vessel de-6[
signed to the current edition of the Code.
That comparison shows I
that the stresses for the Oyster Creek vessel are 25% less than those for a vessel designed to the current Code.
The report points out that there were no inservice inspection requirements in the edition of the Code to which the Oyster Creek vessel was designed, constructed, and stamped and that a vessel designed I
to the current Code, which contains the inservice inspection requirements, would have stresses 30% higher than those for the h
Oyster Creek vessel.
h 1This Report was forwarded to the Chief, Operating Reactors Branch 43 under a letter from Jersey Central Power and Light
(
(EAGS-ll6 of August 1, 1977).
It was submitted in response to URC staff inquiries on the ISI Program previously submitted as s
Technical Specification Change Request No. 28.
r 3A-11 e
f
Rev. 2 "The exposure estimates in this report include only the preparation of the nozzles for examinations.
They do not include exposure related to the following items:
l.
The actual ultrasonic examinations.
2.
The removal of additional mirror insulation may be necessary to facilitate the evaluation of any indi-cations.
3.
The replacement of nozzle shield blocks, removal of j
scaffolding and other items necessary to return the system to normal."
i I
l
}
i I
i l
l e
l 3A-12 I
J m.
,.~--..,____._m....m_--.._-
,,,,-_._..-e-----~ww----~~.----%-.v------~'~-w
-~w~~
i Rev. 2 i
APPENDIX 3B EXAMINATION
SUMMARY
ASME CLASS 2 SYSTEMS AND COMPONENTS
)
ASME SECTION XI EXAMINATION EXAMINATION METHOD (S) j ITEM NO.1 CATEGORY AREAS 'IO BE EXAMINED AND EXTENT OF INSPECTION 1
~
l I
Pressure Vessels i
C1.1, Cl.2 C-A, C-B Circumferential butt welds; NOTE 1 nozzle-to-vessel welds C1.4 C-D Pressure retaining bolting NOTE 2 cl.3 C-C Integrally welded supports NOTE 3 Piping u
Cf 02.1-C2.3; C-F and C-G; Circumferential butt welds; See Inservice Inspection Weld C2.5-C2.6 C-E-1 & C-E-2 longitudinal weld joints in Summary Sheets (Appendix 3C) fittings; branch pipe-to-pipe weld joints; integrally welded supports; support components C2.4 C-D Pressure retaining bolting NOTE 2 Rev. 2 Pumps and Valves C3.1-C3.2; C-F; C-G; C-D Pump casing welds; valve body NOTE 1 C4.1-C4.2 welds; pressure retaining bolting C3.3-C3.4; C-E-1 & C-E-2 Integrally welded supports; NOTE 1 Rev. 2 C4.3-C4.4 support coa.ponents 1Table IWC-2600, ASME Boiler & Pressure Vessel Code,Section XI, 1974 Edition through Summer 1975 Addenda I
a
y 4
Rev. 2 APPENDIX 3B NOTES NOTE 1:
The pressure retaining parts of ASME Class 2 Pressure Vessels (i.e., the Containment Spray Head Exchangers), Pumps, and Valves will receive the same ensination as equiva-lent parts in the affixed piping in the main system flow path.
These examinations are specified in the Inservice Inspecti m Weld Summary Sheets included in Appendix 3C.
NOTE 2 :
Relief from Code requirements is requested.
The Code requirement is to either surface or volumetrically examine bolting exceeding 1 inch in diameter. This requirement is inconsistant and more restrictive than the Rev. 2 g
Class 1 requirement (enmine bolting 2 inches and greater) and later Section XI Addenda, 4
such as the Summer 1978 Addenda (examine bolting exceeding 2 inches in diameter). The in-lieu-of examination for Class 2 bolting will be to surface or volumetrically examine bolting exceeding 2 inches in diameter.
NOTE 3:
Integrally welded supports and support components for ASME Claus 2 Pressure Vessels, Pumps, and Valves will receive the same examination as the integrally welded supports and support components for the affixed piping. These examinations are specified in the Inservice Inspection unld summarf sheets included in Appendtr. 3c.
i l
l i
i
v APPENDIX 3C PIPING WELD AND SUPPORT INSPECTION PROGRAM TABLE OF CONTENTS Table Number Subject Page TABLE OF CONTENTS.
3C-i 3C-1 Code Exemptions.
3C-1 3C-2 Relief Requests 3C-2 3C-3 Weld Summary Sheet Terms 3C-5 3C-4 Weld Summary Sheet Index and Cross Reference to Inservice Diagrams 3C-8 3C-5 Weld Summary Sheets and Notes.
3C-9 i
'l 3C-1 L.,....
_m
4 Table 3C-1 Code Exemptions El Class 2 component connections, piping and associated valves, vessels (and their supports) in systems where both the design preasure and tenperature are equal to or less than 275 psig and 200*F, respec-tively, are exempted from volumetric and surface examinations.
Reference:
Para IWC-1220 (a).
E2 Class 1 component connections, piping and associated valves, vessels (and their supports), that are one-inch nominal pipe size and smaller are exempted from volumetric and surface examinations.
Reference:
Para IWB-1220 (b) (3).
E3 Class 2 component connections, piping and associated valves, and vessels (and their supports), that are four-inch nominal pipe sise and smaller are exempted from volumetric and surface exasnination.
Reference:
Para IWC-1220 (d).
E4 Open-ended portions of Class 2 lines in a non-closed system (e.g., suction line from a storage tank, or discharge line of a containment spray header) extending to the first shutoff valve may be exempted from hydrostatic and pressure test requirements.
Reference:
Para IWC-5220 (d).
E5 Class 2 circtsaferential welds that are not structural discontinuities nor within 3 pipe diameters of the centerline of rigid pipe anchors, or anchors at the penetration of the primary reactor containment, or at rigidly anchored components are exempted from volumetric and surface examination.
Reference:
Table IWC-2520, Examination Categories CF and CG.
NOTE:
References are to the indicated portion of ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition through the Summer 1975 Addenda.
(
(
3C-1 L
l
Table 3C-2 Requests for Relief Code Required In Lieu of Relief Request and Basis Examination Examination R1 Integrally welded supports in Class 1 Voltmetric Surface systems Basis for Relief The physical design of integrally welded supports does r.ct permit meaningful volu-metric examination. This fact has been recognized by ASME Section XI (1977 Edition) and the requirement for volumetric examination only of integrally welded supports has been dropped from the Code R2 Class 1 and 2 component connections Voltanetric Surface piping and associated valves, and vessels that are 3/8" nominal wall thickness or less.
Basis for Relief Volumetric examination of thin walled pipe does not produce reliable results.
Examination results are nonreproducible because of material geometry and vari-ability in operator ability, experience, and other human factors intangibles.
R3 Class 1 circumferential welds that are Volumetric Visual not structural discontinuities nor within 3 pipe diameters of the center-line of rigid pipe anchors, or anchors at the penetration of the primary reactor containment, or at rigidly anchored components are excepted from volumetric and surface examinations 1
Dasis for Relief ASME Code is based upon the structural discontinuities in all systems, which are high stress points. Welds in straight runs of piping are not struc-tural discontinuities, and based on NRC i
Regulatory Guide 1.46, these need not be inspected.
it 3C-2 L
7 Table 3C-2 (continued)
Code Required In Lieu of Relief Requests and Basis Examination Examination R4 Class 2 components of systems or Volunetric Visual portions of systems that are required (if nominal to operate above a pressure of 275 psig pipe size or temperature of 200*F except for exceeds 4 in.)
limiteo periods which are less than one percent of normal plant operating time.
Basis for Relief f
This relief request encompasses the intent of Exemption El, as provided by IWC-1220 (a). Operating conditions are specified in lieu of design con-ditions since the latter are often p
overly conservative.
As a result, no additional burden is accrued in the form of added examinations which would normally be excluded had the designer not gf n extra consideration to conser-vatism. Sitrations where the stated L
pressure and temperature conditions are exceaded by a modest amount will be addressed on a case-by-case basis if the 5
period where the threshholds are breached is of very small duration.
Further ampli-i-
fication will be provided in such cases.
p' 25 Class 2 systems or portions of systems volumetric Visual that during normal plant operating conditions are not required to operate or perform a system function but remain flooded under static conditions at a pressure at least 80% of the pressure that the component or system will be subjected to when required to operate.
^
Basis for Relief These static systems are constantly subjected to system pressure and thus have continuous leak checks. Flow induced stress and erosion are not present. Additional testing of welds in these systems is therefore unnecessary.
r
(
r I
3C-3 k
I
Table 3C-2 (continued)
Code Required In Lieu of Relief Request and Basis Examination Examination R6 Deleted. Not used in Oyster Creek Program R7 Branch pipe to pipe welded joints Volumetric Surface that are Class 1 and greater than 6 inches in diameter or Class 2.
Basis for Relief The physical design of branch connections does not permit meaningful volumetric examination. This fact has been recognized by ASME Section XI (1977 Edition) and the requirement for volumetric examination of branch con-nections has been dropped from the Code.
RS Component welds whose physical location volumetric Surface or within the plant restricts access to visual, as the weld due to such factors as: being appropriate located within a wall sleeve or penetra-tion, in a high radiation area, very high surface Visual during in a room, adjacent to a wall or other hydrostatic restriction without sufficient clearance tenting once to perform examinations.
every 1G yrs.
Basis for Relief This relief is based upon paragraph C, page 4 of NRC Staff Guidance letter of November 24, 1976, "NRC Staff Guidance for Complying with Certain Provisions of 10 CFR 50.55a(g) (Inservice Inspec-tion Requirements) 3C-4
~-
-L.-
._.m.
Table 3C-3 Weld Summary Sheet Terms The following informatton is presented in the Weld Summary Sheets:
Item Description System Identifies ti. system name.
ISD No.
Identifies the Inservice Inspection Diagram (ISD) number which corresponds to the subject system.
ISD Rev.
Identifies the revision of the ISD used to prepare the program.
Line Number Identifies a discrete portion of the system with piping having the same function, pressure / temperature ratings, size, and pipe schedule. This number is the identifying number on the ISD's.
Line Description Describes the beginning and end of that particular line number.
System Class Identifies the ASME Class for the subject line.
Possible entries are:
1 ASME Class 1 2
ASME Class 3 ISD Coordinate Identifies the coordinates on the ISD where the subject line is located.
Types of entries include:
H-9 All the subject area is banded by these coordinates H-9/J-10 Line starts without the first set of coordinates and termi-nates at the second.
G-3 & H-3 Line starts (or terminates) at to B-7 or two locations designated at B-8 to the first two sets of coordinates G-4 & H-4 (e.g., G-3 and li-3) and terminates (or starts) at the second set of coordinates (e.g., B-7).
Wold Type Identifica cach type of weld found in the subject lane.
Possible= entries are:
CIRCUM Circumferential butt welds BRANCil Branch welds in ASME Class 2
.sys tems f
(
Table 3C-3 (continued)
Item escription Weld Type BRANCil
- Branch welds in ASME Class L (continued)
DIA < 6 IN systems with the branch less than or eq :a1 to 6 inches nominal pipe size.
BRANCH Branch welds in ASME Class !
DIA > 6 IN systems with the tranch greater than 6 inches nominal size.
SUPPORT The wold between a pressure retaining component and its support.
IDNGITUDINAL Iongitudinal fabrication welds Circumferential butt welds that CIRCUM BIMETALLIC are also binetallic No. of Wold Identifies the number of welds of that particular weld type for the subject line number.
Required Code Exam Identifies the examination that would be required by the Code (i.e.,1974 Edition of Section XI through the Summer 1975 Addenda) taking into account the per-missible Code exemptions, but not the Requests for Relief from Code requirements. 1he possible entries are:
Volumetric examination VOL Surface examination SUR Hydrostatic pressure testing HYD Applies to Augmented systems NONE that have no code required examinations.
i t
Code Exeroption Identifies the applicable Code Exception Identifier from Table 3C-1 of this Appendix. Possible entries aret E1, E2, E3, E4, and ES Request for Relief Identifies those welds for which a request for relief from Code requirements is made.
No. of Welds Identifies the number of welds of that particular weld type for which relief from Code requirements is requested.
Table 3C-3 (continued)
Item c,*se ri 4t ion 1
Peason Identifies the generic helief Request lientifier from Table 1C-2 of this Ap['endix.
Possible entries are:
H1, R2, R3, R3, R5, R7 and R8 In Lieu of Identifies the examination to be performed in lieu Examination of the Code required examination for those welds for which relief is requeated. Possible entries are:
1/2 VOL Volumetric examination of accessible portions of the weld (s)
SUR Surface examination
!!YD Hydrostatic pressure testing at Code sl ecified frequency PRS paessure testing overy 3 1/3 years FIR Flow testing every 31/3 years No examination or testing in to be NONE performe s.
- NOTE: See Report Section 3. 3.6 for discussion.
Notes Identifies the note number which presents supplemental or explanatory information for the Request for Relief or examinations performed in excess of code require-ments.
/
L r
Table 3C-4 Weld Summary Sheet Index and Cross Reference to Inservice Diagrams Wold summary Inservice Diagr.am System Sheet Pages Number Isolation Condenser 1-5 JCP-1941H Poison 6-7 JCP-19419 Containment Slaray 8-11
.!CP-19420 Reactor Recirculation 12-14 JCP-19421 Core Spray 15-20 JCP-19422 Main Steam 21-23 JCP-19423 Reactor Shutdown Cooling 24-26 JCP-19426 Reactor Head Cooling 27 JCP-19426 Clean-up Domineraliser 28-29 JCP-19426 Feedwater 30-32 JCP-19426 CRD Hydraulic 33-34 JCP-19426 Drywell Equipment and 35-36 JCP-19426 Floor Drain Sump Demin. Water Transfer 37-38 JCP-19426 i
Mx. Bldg. C osed Cooling Water 39-40 JCP-19428 l
3C-s L
~
I f.!),bj n a o-7.i;m
.i l1]
i e
i je 3! p
!. "i s ":
d
-!"< i 3 3
Y!
?!
J
. I.
l y
- g
,; 2 :
2
- i
{
l 2;
t C
s n
.n e
e e -
I
-l t i j
si s.
II k
i h
d 4
M.l 13 5 5!
f15 3!
ff WAf f3!
.i e
n n e
n n m..
v:I]
b E
e e
S f wsi!rl=3 W I, v [= vla s! s s
s s
s=
=
J p-j g
lj r
rr r i
c-t si I
y n
N.
.Y 7
A.
I b
d d
i I
p I
s o
n 3
3
=.
a g a
c c
si b
~3 I
3 3
~t
'f y
y 26 Si r
r at 3%
[
j 4
A al al T
2 2
5
- - 3 m
7 I
T 4
a c*
c*
2, E,
l I
y I
E5 r3 Y
Y g
y r
r f
=
I j
r s
s s
s s
s 7
7 7
7 J
f i
?
?
W W
W W
=
- 1dIif.l
,3 4 al I
4 i
i la
.' 5
.p } l C.2 2C.
.C.C
.G.2.:
2a.
C.C 2.
~
6 tv r, e :
,e Ji i:
l
$$$e
$$E
$C.
- ,i t,';
e...
a *j;
~_
~_.
2..
d r,
sj s m'
1 5*
t
~
cF i
33 ff f
15
!!5 f
f5 5
5 55 l
jj I
~-
=
.2
~_
lI 1*
~
s=s s
1 s=
s
=
=
s s
=
i
_sl
_E j,
_sl}
_! l
_?
_! l c
=, j s
?
1 E
9 2
2 5
~
~.
~.
g g
e a
y
!vp
!!p Sh A
niv I
j!v l-A+
E jn et e-a
-s 2
t e
j
- us
, v.
U,,
XlI
.X.I
,i X8 X;
X,' 8 i
s zij l
k 3
b"5 bb b:~g b5 h
z.
re r
i si]
q 2
4 ha u,
a 5'e3
_53_
5'E y
.h u
A-3' 5
s
.n
- t 5;
i h
h h
h l
3
+
+
+
+
+
+
1 V
W Y
W X
y
=__
n, i y
m
~
> g sal 3
3 11 1
53 EE-E?i' E
3
?!
~
l e
a 3
'j
..s 2;
==
s j
i E
i s
~-
-..a g-.
a
-n
~~
y g;
I 4
bl E E
}7 1
}u vin v
vue e
i e
vi si en Ie j jj
~.
3..,
~.
lll 3
=_
I.lil!!_1111_!!_!11_li j
t R$
8]i!
5 5
o s
s ce 4
p
~
~
h k.
W
- a. b J
iI j
a" G
EA 7
a 1
v vi g
g e
r e
I I
A e
1 A
l-E L
e
+
a
=
- j s
g 3
4 3 f A
3 8
S X
3
{
i 16 36 3
i g
i 8
5
.S. A.
l' i.
5?.
- r s
r b
(
l 3 >t
+
+
+
+
~
v v
v v
v
~
1
\\
som -
Q
~
=
4 y
5 1
3 3, s. s
)
A 3d 5
3 5
1
- '3 i;$l l
e 0
~.-
e 4
4
[
k 5 In j
}!
lll
=~-
b a
-1 I Ill lij j
l11 ij !
I la
)
1 h
l en i
n
?
?
y l
i 4
b !!
i
!f
$8
![
(,
.l u
y b
N*
L
_- - ____ x
7 _-.
J Para 5 ef 40 OYSTER CitEEK IIUCLEAR GUIEAATIIIG STAT 10It le0TES system:
Isolation Condenser 158 Ito. JCP-1M18 1.
Welds can only be volumetrically emesined from one side due to insufficient axial clearance.
2.
Walds located inside penetration are inaccessible for volumetric or surface examination 3
Welds located inside penetration are inaccessible for volumetric, surface or visual examination.
I 1
l
9 R
R bill 3
3
~
E bl l
i 13
=
I 3asl!
}
i b
T 22 2E 2
i
't
.~
~~
~
1,
~
8 i
i
[
E 5
I N
3j jf e-
~n 4
I i 3
s
!!.! !.!. l !.!
gj I,3o l
s 5
~
4 s
ja W
V f
e r
i f
it t
6 3
i i
I r
e c
e f
f s
f, h.
I S
I e
.s
.s 3
.i i
i
3 Page 7 of 40 OYSTER CIIEEK IIUCLEAR GEIIEllATIIIG STAT 10el IIOTES System: Poison ISD 100. JCP-19419 1.
idelds located inside wtration are inaccessible for volumetric or surface examination.
2.
idelds located inside biological shield are inaccessible for volumetric or surface examination.
i i
I r
l
r I
I Pues 8 of 40 tenetstytCE teePECTaone rem.am n
synessa t-st ewsT spur Proposed Dr M-LLOYD 8-5-19 y
IDELD SuassaAAY SHEET ISD No JCD-t*423 Bar, O Approved By M. M. ASEWITn CMIEF Eur. theta t-24-19 Ovueur Cseek tausener e
. Summen R c a tw Refer Spensum ISD No. of Code Cede No. of la Im u of Kane %seher g
Lans rharwqpsman Omas Comsdmose Weed Type Sekts Esan Esen s e Welds Reason Ea = --taan Notes eqZ-t-16" TantE T::st;;5 T3 SuCTt3m mEADER LleES 2
3-6. S. 9 ClaLin 3
VOL t-4 Sua t.2 CiaCLue 3
40L 3
en FLW 2
gaAnce 3
VOL E-4 Sua
.2 eqZ-1-27 kCTs3m MEA Ea T3 C3a1 & C3mTAls-2 0-6/3-3 ClaCm 8
WOL g.4 i
l pint SPaAf WCTB3c Sua I.2 h
Cl aCW 34 WOL 34 ILW 2
taAnta S
wet L-4 Sua 1.2 scPPCa7 a4 Son eq-t- t r Fa3e kCTt:ss MEA:ta T3 PysqPS t-t &
2 g.y go F.4 Cla p 21 W3L 24 ab flu 2
t-2 s n-6 3
e4 Pa5 SuPPoni 3
sua aq-s-t r FR3e SUCTa3e s:(A*.Et T3 Puses 3-3 &
2 3-8 to F-9 Clacun 29 WCL 23 FLW 2
t-4
& G-3 6
e4 P45 LCeC.
I WOL I
ab FLw 2
SUPPCAT 4
Sba aq t r re3e Ptres I-t & 3-2 T3 t&* a tr 2
F-6 s n-6 ClaCLn 16 v3L e6 m.
Pas at3utta Amo tv = 14 a tr assuC-TO 5-5 teG Tit W aY 2
53 eq-2-t&*
Fase tv a 1 r atsutta ano 2
C-5 to F-4 ClaCup.
29 v3L 21 e6
- 5 te. Iv. E r at3uties.gg T3 s n-4 etar a Cnamsgas s.3 a s.a g,,,,,
go, eq-2-t r f E3e PbmPS t-] & 3-4 T3 17 m 14" 2
F-3 & m-9 ClaCust 14 W3L I4
- 4 Pa5 at3uCER An3 l e a I P a 34" aE3UC-73 m-to ItC T11
%P90a7 2
Sua
9 9151 j
~
d:
il 3l E-EaEa EaEa5-5 EaEa-i
}
3
$ 5s t
i
- iii, iiii
- iiii, i
1 l
jj s.,
--~
- l 11 m Il g@
g en d
M N
- N g
en M
M i
i l1A I !!!
! i l l i
! !i l l i i
[
I$
h.
E 5
I i
I 3
4, I
jj
~
~
l 8
.g i
,j eMj is!
,s1 Ie t
s v
c Es Xe r:l;-
4 5
[
X 8
8 syv
- z
.j9 9
5 :.,
1 g
.z{-
c.
08
- i 3
s zl-
- l99 a
- '8 l
h-(s r 4
- 'i 1
y!
55 I
!$i
!E l
i s
s i
j 4
4 4
A t
t t
t t
'it'
w~
w_
\\
_-y
^
Pay to of 40 s
a n
spansas Caratam eT 5pese N leWGCTIEW FWAGRAAB Poses g a,
- m. tLovo I.5 79 WELD Sulmammy meEET 330 m K P-t3422 3,,,
o 8*
Ogumr C m lheter W Samen Appygegg gy M. N. A5sWITw, CMIEF EmGlh(ER t-24-79 Amewest for Ret.ef Guammen IED sse. et Code Code Iso. of In lasu of Kame -
Ems W Omm Ceessansas Wald Type Welds Beams Debte R7 -
r- -
hates et-2-4*
pase 14 a tv a e atsucius Ttt 2
e-3 C-3 Cittun 13 wet to a4 Pas t#57afAst OF W-23-5 73 Teams 34QAsn getag t Ling 3
R4 RW 2
StamCM 2
VOL 1
R4 FLW 3
ha i
SePPORT 2
SWR at-2-4*
FSD 6* a 6* a 4* DigyCtas Ttt 2
3-3 CitCum 36 wCL t-3 i
R4 PRS T3 sa w v m antaatt test 984 se 2
wot E-)
1 Sua 8
PtaET447:am a-M 2
s-5
$#Poef 2
sut as a>=es e
at-2-lb*
Faen PfeETRAflan 3-46 73 2
S-S CleCust 7
VOL 7
84 FLW IW" a IW" IP mESWCIE TEE UPSTaEAss GF SPGAT EIES aq-2-12'"
FaQue IW"al4 mII"* BE3bCteG TEE Aa8 2
5-8 ClaQPe 12 VOL 12 Ak FLW t&* a 12* aE3pCit T3 CaprasasuGWT SPGAT 884 5 at-2-f*
C3WTasassiuY 574sv aleES FEst 2
C-8 CitOpt 44 DOL 44 a4 FLw 32* a t= assuCses gesusTagen er PfetTtAT88s 3-M at-2-84" PEutTRAft3m E-4) 2 3-7 SuPP947 2
Sut I
R3 h *st 4
at-2-8&-
FR3e PteETtATite E-4) T3 34" a 82""
2 S-7 CIROJR 2
WOL 2
R4 FLW atancias ELams at-2-IP Fage14" a 32" attuCleC Etagw 2
S-7/C-7 tt vel tt ak FLw T3 32" a t* aE3sttes as TE CIW CanTasauteT SPtAT asets et P CantatenteT SPeAT asess Fece 2
C-7 CleC24 43 b;L 4)
R4 fLW 32" a 3= mE3WCras 90se57 tease OF PfaETRAll38 E-4]
f
w-,
Page 11 cf 40 OYSTER CREEK NUCLEAR GENERATING STATION I
NOTES System Containment Spray ISD Mo. JCP-19420 1.
Asgaented exam on penetrations by surface examination. These welds are extensions of torus.
2.
Also visually Inspected during ILRT.
3 Wids located inside penetration are inaccessible for volumetric or surface examinations.
4.
Welds located Inside penetration are inaccessible for volumetric, surface, or visual examination.
l
eli l j
g s.
ji e.
- e. e.
5. -a a.
e.
- e. e. a. -
s.
- e. e. e...
~
)
~
a 22 1
-j j f
- ~.:
E.
.e i
g 49
~
n n - -..
a.
~
~~-..
o.
~
~~
Q
-=
E b
a s a
~
d5 d d56 d5 I50 50 I5 d5 I EI l=j ll 5
~e s~
~e e~
e e-
~
s s
s s
I'
)
3
,i 3
,e 3
.5
~
53 5
- g 55 Ef 5 55
.45 5
=8 5
l
i
.h !.!
l.la*
.s 3
.s.i.s
.! aE.V.3.s.r.s la t
ea 35 9
4 4
4 a
i
~
~
g 4
4 a
p 9
5 P
9 il l
V 3
4 x
3 n
C Q
Q 5
e E
N 3
n 3
2 4
W 4
i a
I N
f N
f N
l g
g 5
5 h
w
- v a
b 5
Y Y
y v
v v
v
il a
y bg
=
=
a n
s1a's a
n nnJa 3
a
}
2 4 54 2
l 3
2.s 2
at j
'l
~
~ ~-..
g
~
~., - ~..
g b
3 n
i j[]
i i'=
a
}
b, o,
.3 t,
O, i
i, j
gj 2"
"2 2=
2" "T
"2" 2"
5 5&
u 4
Xi a
u
.i 5
j s=
s! s
=5 ss s! s
=E s
.s.i
.s i.s.
It
.s.3
.s.i.s
.ll 5
i
.a a
Si
=
=
y5 9
=
e e
A
~
~
l 9
4 4
8 jj O
?
U
=
U
=
0
{
}
}
U i
5 i j
e
=
j 3
2 l
r.
r c
e, 3
d a
A
)
g n
I v
o a
x a
e 2
El k
L 9
.t u
a a
3 t
Y t
a v
v v
v
Pcg2 14 of 40 OYSTER CREEK NUCLEAR GENEAATING STATION NOTES System: Reactor Recirculation ISD No. JCP-19421 1.
Welds located inside biological shield are Inaccessible for volumetric or surface examination.
l l
.h
A e
$141
,1 q-4 21 f
E 3' I 3.: 00.
300.
3 E L.C 30.0.
20 y
1 i s:g 2
3 5
f
- .i*
.2".
ii 2i
- i i
5 1 3 5
,a
,m
.a e-
-o
,-=.
o..
.g d
i i
lln 4 -
8 vl I
OE 1
A 1
i a
2
.s 9
3.,
3 lI
,m g
--m m
e
-m a m a -
m n
=
I I
! !!n! s!la!!!!!!11!!!!!!
ss ss-E s
s s-s-
s-s-
l
-s i
e a
e
,e
,e
?.
?
?.
Is
.a 4
4 4
4 o
p O
E-3 C
C C
C C
a h
.h h
h I
h$
$w Y
6 M
m m
j
=
5 5
5 5
r v5 2
r r
v N-
- U
-s 4
N
~
Se
- z 6,
v
- g-
?
i 30 33 5;
di fh h-h s
at ga 5
as th as u-g tu
.2 s
s s
s s
J
+
+
t
+
+
+
+
2
=
v v
v v
v
\\
s a
Page 16 et 40 n
Systeem COR' SPRAT IAMRVICE MlWI PROGRAas Pseposed Dy M.
LLCvD tWELD SuasasARY SHEET 1&Z3_
ISD h JCP-19422 Ser. O oyemme caenk shnamar em messie Smeen Appeuwsd Dy n. n. a5uwitn. CM!st tusset tR t-24-79
~
Requent fue Relwf Spessus ISD No. et Code Cade No. of la Lwu of t.m. Member Eme Damenstaan Oman rw-wekt Type teksa r==
Enemipaaun Wekis Reason Esammutam Notes i
j m2-2-10" FR:se t a to" REDuttR achas5TREAn 2
F-8/s-6 CRCum 35 WOL 35 R4 PR5 CF PunP m203-A. TWADuCM W-20-50. TO 8" a to" RE3UCER UP5TREAfe OF gg 7
gg pgg V-13-12 SUPPORT 6
Sun l
l 1
m2-2-t*
FRan &* a 10" AfDUCER 70 VALVE 2
3-6/8-$
ClRCUM 1
WOL &
9 R%
PRS l
l V-20-12 SantTALLIC sut i
CIRCUM 7
VOL 7
R4 PRS SRAeCM i
SUR I
R4 PR5 SUPPORT 2
SUR l
m2-2-6" FRan 8" m 8" = 6" RIDUClieG TEE 2
3-6/G-4 CIRCUM 26 VOL 2
R4 rRS l
AT V-20-27 TO TORUS WACUun BREARER Llh(
gg gg ggy SRAseCH SUR 84 ILW 1
SUPPORT 3
Sun m2-2-10" FR0n to" a IC** a 10'* Ytt UP5TREAn 2
C-9 to 0-8 CIRCUM 16 VOL 16 R4 PRS OF V-20-50 TO 10" a 12" REDUCER 5
& 0-7 AT PUMPS m:03-4 a m203-C
,,ang,
gue R4 Pas SUPPORT I
SuR m2-2-12" FROM 10" a 12" REDUCER UPSTREAR 2
0-8 & D-7 CIRCUM 4
VOL 4
84 PR5 OF Ptses m203-A & C To pumps Rn3-A s C DRAteCM 2
$UR 2
R4 PRS SuePORT 2
Sun l
R2-2-8" FR.m CORE SPRAT PUMP 5 R203-A & C 2
D-7 & 0-8 CIRCUM 22 VOL 22 R4 PRS f
TO IS" a 10" m &* REDUCING TEE To C-9 OcWIuSTREAn OF W-20-50 maamrH 5
5UR 5
R4 PRS t
SUPPORT 2
SUR l
l l
l
5 1 51 i
~.
z 1
~
I 4
E il 3ng ree-a is a
un a
e r
3 j
s a sa 3
1 s
1
,l
==
- =.:
i J
.g o
a
-n
.~
-~
-~..
a egn 3;
i
,g x'
f s
a
$t a
a 1I 1,
s J'ja e.s. s. s -.a e.
- s. s,
- s, s., e e. s.
- s. e. s s, s
e s
e.
1
,1, n
I}
s ! =i n -
-n n--
n
-n i
1 e
e
.i -
I 1
s s2=g s
sa s5 s
=s n
e se s = s s
=s a
1 as}s, vs e
wr v g
i, arvjg lI ss.
se a
sa ss i
sc.
a
- s l,
b i
I Y
a g
u u
a u
a a
4 4
a 4
n
~
n r
5 6
2 5
C.
j 3
t NB S
a L
2.
A R
a v
b S
+
0 4.
94
-4 4
e 3
Lr eg 3
A
- y W.
3 4
b
.y
- .m 3,
y y-g s5 g4 3r v
u d es:
-e r
r V
g a
=
J
+
+
+
b b
2 V
V 2
7 h
l l
~
R o
T bi b i
e
~
1
~
=
T
%ea r
5 Ej a =
=
==
=
T T Js Ef' ES E
EE'S f
E 5 20 5
j fi.
2; 2
22.E e
r*
2 2
3 g?
.a..
-~
, N
.~
E
- 2 zs S
a x
$i" a
1 4
I O
i E
af s.=.=
s s.s ss s.s s 28 gag
~
W M -
W N a
-N O
N N
=
z3
.a8 i'
s.
k i
I>l 5*E EW 5E EN 5 E
I G"'
3 Wit
=
la t
Mt MW e g!
sia so sa ss s i
g i
I W O 4
m yej e
4 e
i sj r
=
4 a
t h
j W
o u
I
?
E o
9 I
k 2
A j
A b
k 4-3
-s s
5 i
=
e l
1~
s1 5
tw 5
as s
=
j a{9 ra rt C
d g
3?
35 5
a3 m=n
=
5=
a a
a A
A A
h h
h
'e w
e-*+-%~--w-rmamo*-
1 Page 20 of 40 OYSTER CREEK NUCLEAR GENERATING STATION NOTES System: Core Spray ISD No. JCP-19422 1.
Also visually inspected during ILRT.
2.
Welds located inside penetration are inaccessible for volumetric or surface examinations.
3.
Welds located inside steel box around penetration are inaccessible for volumetric or surface examinations.
1 4
4.
Welds located inside biological shield are inaccessible for volumetric or surface examinations I
t i
i 5.
l Welds located inside penetration are inaccessible for volumetric, surface, or visual examination i
t 1
l 4
l I
(
l l
i i
i
[L -
N *89 9 g iji j
~,,
~
~
~
z 1 "8
=
=
a a
jI 3
EE'a El E3 3
2E S
EE Ea a o o -
o -
s o o 1 a,
G 1
2 s
e
)
a 24 3
a w
r a
T2.E 22 2E T
T2. &
TT TE v
=
Z<
g W
Qe g
33
~_
_~. o Z8 S.
E Z
Z il
.=
g
}
E a
i 4
]jg
=.= s. s. = x.
- s. s.
s s.
s__u s.s s s.
88 s s.
a i
-yo 1
i I and -
g
_~~.
m _
_o
- o m _
.I o
g C
d
n d
n n
n
~
E5 E E 5 5 Ea Ea 52EE58 E8 E8 I
G 1
=r==gt
==
==
=r==gt
=t
==
OECG.3 GS Ga G.GG.a GS G3 i
I Y
T l
GIG R
7 E
R T
E i
(
=
9 v
v
=
9
- q l
I I
o b'
W I
s I
o g
=
R 8
1 E
E 5
j y
3 y
3 O
f g5 2
5 32 5
a a
a c
A a
c A
~
Eg 4
3 5
3 I
t-2 t
O!
g t
O C
C
?
C
.!5 5
.!.=.
5 3
s s
s s
l l
,,,r.
u u
--a s.-
u
=
e.---
e-A m--.---
O z
ob en
~
W I Jg 3'
Ea 3'S s.
5 5 na g
b w
I p 1,
ll 2.
EE 2.E I
o
" 1 d
d m
~ ~
ss ~
2 lli Z*
O I
N i
i I
a#
$I d4 g 2-- ge 1 5 li Og E gO ~ a g g 1 o o o a e e s b 3 u u u m Y 59i e ? m g35 9 4 ? E to ? ~ j p a. !c .g 3 8 2 52 R 5 t~ a: "ma g7 ~ T 84 ? 7 5 a"o s j" =g s 1 3 a a a re gan C g7 as .b? .7 60M = 6 I= N N s s M -~.1----... _____,___...____.-_._._._.-_,,__-.-..._.-..4.. .w., ,. -. r.. i a
Page 23 of 40 j t i OYSTER CREEK NUCLEAR GENERATING STATION NOTES i System: Main Steam ISD No. JCP-19423 1. Weld can only be volumetrically examined from one side due to insufficient axial clearance L I 2. Welds located inside penetration are inaccessible for volumetric or surface examinations 3 welds located inside penetration are inaccessible for volumetric, surface or visual examinations. I l i i h l l \\ 1 l 5 l L
l l Pays 2% of 40 [ n System REACTOR SMJTDOWN C00 Lites Prepamt by H. LLOYO l-2-79 y WELD SUResRAflY SHEET ISD No..lCP-1%26 Rev.A Ovseur Csunk Musher commenes sNeen Approved By H. H. ASKWITH, CHIEF ENGINEER I-24-79 i t onee Request for Rehet j Syseman ISD No. of Code Code No. of in Im u of EJae Nussber E.ine Danctlpean Class Coasdinate Wald Type Welds Esam Emess-Welds Reason Examinataan Notes NU-4-14" FROM RECIRC. LOOP "E" TO VALVE I F-7 CIRCUM 2 VOL I V-17-19 SRANCH = 6" l V0L I R7 $UR 1 Nu-1-14" FROM VALVE V-17-19 TO PENETRATION I F-8 CIRCUM I VOL & x-7 SIMETALLIC SUR CIRCUM 12 VOL I R) NfD i SUPPORT 5 VOL 5 Rt suR 1 l' L i PENETRATION X-7 i F-8 CIRCUM i V0L 1 R8 HYO 1 SUPPORT I VOL i Al Sun Nu-t-14" FROM PENETRAT10el X-7 70 14" a 10" 1 F-8/E-13 CIRCUM 19 VOL 1 R8 HYD 1 i REDUCER i I R3 HYO BRAseCM i 6" 3 SUR SUPPORT 4 VOL 5 RI suR l Nu-I-10" FROM 14" m 14" a 10" RE0uCING TEES l E-13/0-l3 C IRCUM 85 VOL I R3 HYO I AND 14" a 10P' REDUCER TO VALVES V-17-1, V-17-2, V-17-3 SUPPORT I V0L I RI suR Nu-3-14" FROM RECBRC LOOP "E" TO VALVE I E-7 CIRCUM 5 VOL 4 V-17-54 alwsCM > 6" l VOL I R7 SuR i sRANCH < 6" 1 SuR i SUPPORT I VOL 1 R1 SUR 1 Nu-2-14" FROM VALVE V.ly.54 70 PEleETRATI0es 1 E-8 CIRCun i VOL & x-8 BlMETALLIC SUR CIRCUM 4 V0L I PENETRATION X-8 I E-8 CIRCUM i VOL 1 R8 HYO I l i SUPPORT l VOL I RI SUR i I
sn 6158 i z o$ = n V 3 3 3 ER a E'a j g a 34 a I i 1 a 2.s a .I =- 2 g j,4 O i i II & E b 9 l Ljj ffig f51 ElB M -M M M M e g Li vi, wl, a 1I I *Ila, "via3 l1 x s .n = p 5 3= f. 6 ER A l l I 20 l .t_ l I A.? !? i e
== 3 ,Wa .A e' W O r ~ l I E53 R$ -Et It a I = i 7 7 n M i i 6
f Page 26 of 40 l ( 0YSTER CREEK NUCLEAR GENERATING STATION NOTES System: Reactor Soutdown Cooling ISD No. JCP-19426 j l. Welds located inside penetration are inaccessible for volumetric or surface examinatinn. l l l I
9 18: 1 3 o'? E i 1 ~ a a3 5, I 3' g .s 5 5 5 ~ y } _? a sa 3 j 2 0 =2 2 i s e M s n i i i I at di a l=8I ~ s s
- e. s. e..
1a s D 1
== $I E s Ij 8 2 3 ,g o o s 5 .t es u u v u 355 9' ? ? t J t = ?. i 3 l p i a 3 8 N W e av 8 l 5 3 - 3 Q a a j d R 0 y $= 0 0 $ 3 6 e a >= aa= 4 J 58 L L = g 2 02 9 = g. 3 lg "5 5 335 7 s 30==g-l 25 ma r r ma ^ b b 4b j u? ? ? ? = 1 o gu h l l l
Pase 28 of 40 n sysseen (LEAm-uP DEMINERALIZER W Dy M. LLOYD I-3-79 i y~ WELD SUhlAAARY SHEET ISD No. _ JCP-89426 Rev. O Oyseer Cseek Deuelmer *- . Squemen Apswoved By M. M. ASKWITH, CHIEF ENGINEER l-24-19 m a.qu e for nes r Syansan ISD No. of Code Code No. of la 1.seu of IJae Nunnbar IJae Descrip4&on Cimes Coordanese Wald Type Wekle Raaen Exeunptaon Welds Rm Esaminat.non Notes led-I-6" FROM RECIRC LOOP "B" TO PENETRAT1001 1 H-6/N-5 CIRCUM 13 VOL X-9 tRAmCW < 6" 2 SuR t $UPPORT 3 VOL 3 El Sun PEnETRAT10el X-9 1' M-5 CIRCUM 3 Vol 3 R8 Hvo 1 SUPPORT I VOL 1 R8 maus 2 i 100-1-6" FROM PENETRAT10s X-9 TO VALVES I M-5/M-3 CIRCUM 12 VOL 12 48 HvD 2 V-16-2 Asso V-16-14 MM < 6" l 504 i R8 HvD 2 100- 1 0- 6 " FROM RECIRC LOOP "r' TO PENETRAT40s: 1 F-6/F-5 CIRCUM 12 VOL 1 R3 Hvo X-10 BRAIICM 4 6" l SUR ~ SUPPORT 2 VOL 2 al sum r PENETRATl0ll X-10 I s-5 CIRCUM 2 VOL 2 R8 Hvo I SutPORT I WOL I R8 Nh4 2 N0-10-6" FRSS PEMETRAT1080 X-10 TO VALVE 1 F-4/F-3 CIRC # 6 VOL R8 HTO 2 I SRAasCM < 6" I SUR I R8 HYD 2 l l i i i
i i Page 29 of 40 i OYSTER CREEK NUCLEAR GENERATING STATION NOTES System: Clean-Up Demineralizer ISD No. JCP-19426 ( 1. Welds located inside penetration are inaccessible for volumetric or surface examination. [ 2. Component located in a minimum 30R/HR field. Alternate examination will be hydrostatic test for piping t welds and n3 alternate exam for penetration and support welds. h l I I i i i I i I i I i i l I l I l l 4 i j l i l
,_.m, 4 ma, am .a-_._a.,e%e_a_a_a aa.a._a ._______a_, .u_44 _,,__,_,._m O em N N a. y 4l i i ls 2 o ..o o. ....o . o. a nasas a a ss s sa a ssa } i 4 53 3 } j j u
a=
a ..m
====a =
- sa i
j,j g e o e N i = h l e IwM es e es d W 4 -j jj _m fll s 8,!. i, s ,1, i i r
- _n__i_,
ul.rij _n,i Ij u_ni _u_ _n y 91 133 8 ? ?_ ?_ =_ A A ~ ~ I jj 2 2 5 g 2 2 $= h Ig 5 ,I g e-e e ~ us n e nn = 2-2 2-2 I .M b 2 sU s s = 3 58 E. = s* s= u I &I ? Eh EN 1 I Ik .E.,U" 5. .E. u N 3 5. I k bs i ja p s.- se s= se sr e ce e4 ee me 3 7 7 7 7 7 7 3 7 7 7 7 7 7 k k 3 3 3 3
i N e' N 2 O- _7 3 51 ja = ' a-I a Ea E i 5
- 3 EE
8 h E d AQ 5 J!
- f 5
) ..a 2 ..s .a : s
- a i
s s 3 g] ..m e-e ZN g U i i i V k E b j s a., .,6 . a... .. e e., .,f s. i Ig 2 .m e a. m -- m -- -- U L k g 5*{ 58 5*{ 5 *8 55 5-ij 8 = w- = i m a = i =- vg = m m_ 9 3 g 1 ? ? ?. ? ?. o o o I I p O ens 8 R W W W X r E r b 2 R R = n 7 ? A A j SA a s a 8 a = r j av v v v g g -j = = = g s-ss ss s: = w me =4 e4 e4 = r 3 7 7 7 7 3 7 7 7 7 2 k
Page 32 of 40 OYSTER CREEK NUCLEAR GENERATING STATION NOTES System: Feedwater ISD No. JCP-19426 1. Welds located inside biological shield are inaccessible for volumetric or surface examination. 2. Welds located inside penetration are inaccessible for volumetric or surface examination. f i i i i l i i i i l
._a_ _m ,,4.e_a -.a m e-------------e' $jE l -] "' ~ a s e z ~ c ~ ~- il si E 1 Jg E aI E3 '3 p g 3 % e a .j = g } I i E g q i ~ e a su ~ O b 3{ i a I tu y a. ig lJ 4= Y 5 y I 3 'E p ss s sa s - s i s! ! E. EE M 5 6 I e XI5 E I 5 I j l 13 i i, O O w k 0 e 2 E = 2 s l d A e a Es s 3 a E 5 h E S 9_g = E5 I EE a 5G G sb er r ta = EI= r, r m o E N a,
I Page 34 of 40 OYSTER CREEK NUCLEAR GENERATING STATION NOTES System: CR0 Hydraulic Return ISD No. JCP-19426 1. Non-load bearing lugs. 2. Welds located inside penetration are inaccessible for volumetric or surface examinations. ) 3 Welds located inside biological shield are inaccessible for volumetric or surface examinations. I l i l l i f i t
il5 I h 1,1 21 3' s i 5 } E E ^b i e a '} 5 1 i i i t Q B o = i g ens a .l [ ? ? 5J E = x ~ l= ~ h 5 s a s a M E u u 9s 1y5 8 e, t, I p i a h 5 5 = -i e l5 $0 N 9 9 y e 3 a A_ 8 8~. i i II E E5 [ E Ei ) I
Page 36 of 40 l OYSTER CREEK NUCLEAR GENERATING STATION f NOTES System: Drywell Equipment and Floor Drain Sump 150 No. JCP-IS426 R4 applies; however, surface exam to be performed as augmented exam for penetration. 1. i l \\ l l l l I I \\ l l l \\ l i i l l \\ \\
5 16 1 ? R 2 ~ 1 4l.l 5 i ~ E } ql 55j .E I
- j E
= y g 5 3 b b .2 i. l l 't ,5 j, S 4 i i 4 .?? ? .? g g 6 .. = = 11 In 4 gh _ m ___~ U i I f l 5E* 55 l 55 55 u u u u j I il sj' e e_ l y 5 a}k N we e 5 2 0 g 2 A 5 0 5 l 5 5 I l 5 l I 3 E_ g = 23 }l 50 i ss 2A e es 4 A
\\ l Page 38 of 40 l l 0YSTER CREEK lt0 CLEAR GEllEAATileG STATl006 It0TES i System: Domin. Water Transfer ISD No. JCP-IS426 I 1. R4 applies; however, surface exam will be performed as augmented exam for penetration. 'i 2. Penetration weld is inaccessible for volumetric, surface, or visual examination. l 1 I l I i l 1 1 4
- l.
i i gl,{ l j 3 2 L t 1]. e s 11 's I s } j 3 m$ 8 ue 8 I j u = u a u l = l' 3 a 1 e a, l E i i I l .i * $l i l }} fjj f 3 i f Ic j jg I ) 5 i s s j s l ? .s .M .M .s j o j gla l 1 = = = = 8 4 4 4 4 4 4 p i l a i o C e V j E ts j j e sI e n e A i! l j = a si e 1 E lE h! l k e 4 3:I 3 4 Ar 5 !s s E A s r> !s a r: 8 !"3 3 5.5 5y 3 .It. .w s s J A A j. b b b ) v---wn-e --en,,-m --.,,-wr --e---w- - - - --www----w- ,wam,- - - v-w ,m,- - -
Page 40 of 40 OYSTER CREEK NUCLEAR GENERATING STATION i NOTES I i i System: Closed Cooling Water ISD No. JCP-19428 1. Relief from volumetric exam is requested under relief requests R2 and R4. However, surface exam will be performed as an augmented examination for the penetration. 2. Lelds located inside of penetration are inaccessible for volumetric, surface, or visual examinations. 3 Relief from volumetric and surface examination is requested under relief requests R2 and R4. A visual exam will be performed during flow test. i l i ( i i l 4 I i f f I l l t i a .}}