PLA-3165, Forwards Rev 6 to ISI-T-100.0 for Unit 1 & Rev 3 to ISI-T-200.0 for Unit 2 Pump & Valve Inservice Insp Testing Program
| ML18040A927 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/10/1989 |
| From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17156B066 | List: |
| References | |
| PLA-3165, NUDOCS 8903220018 | |
| Download: ML18040A927 (6) | |
Text
ACCELERATED DI~BUTION DEMOYSTR+lON SY) TEM 1
iS REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DOCKET N
05000387 05000388
SUBJECT:
Forwards Rev 6 to Unit 1
& Rev 3 to U it 2,
" ump
& Valve N
Inservice Insp Program
".~ g/j DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR TITLE: OR Submittal: Inservice Inspection/Testa g/Relief from ASME Code ACCESSION NBR:8903220018 DOC.DATE: 89/03/10 NOTARIZED:
NO FACIL:50-387 Susctuehanna Steam Electric Station, Unit 1, Pennsylva 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION KEISER,H.W.
Pennsylvania Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R.
Office of Nuclear Reactor Regulation, Director (Post 870411 R NOTES:LPDR 1 cy Transcripts.
LPDR 1 cy Transcripts.
0500038 05000388 RECIPIENT ID CODE/NAME PD1-2 LA THADANI,M INTERNAL: ACRS ARM/DAF/LFMB NRR/DEST/MTB 9H OGC/HDS2 RES/DSIR/EIB EXTERNAL EG&G BROWNi B LPDR NRC PDR NOTES:
COPIES LTTR ENCL 1
0 1
1 6
6 1
0 1
1 1
0 1
1 1
1 1
1 1
1 2
2 RECIPIENT ID CODE/NAME PD1-2 PD
/
AEOD/DSP/TPAB NRR/DEST/MEB 9H NUDOGS-ABSTRACT R ~ILE Ol EG&G ROCKHOLDi H NL 007 HEMMING NSIC COPIES LTTR ENCL 5
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1 S
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A NOPE 'I0 ALL "RIDS" RECIPIENIS:
PIZASE HELP US 'IO REDUCE WASTE.'XNZACI'IHE DOQJNERZ CONIROL DESK, ROOM, Pl-37 (EXT. 20079)
TO ELDGMATE YOUR NAME FRGH DISX%KKITIGN LISTS POR DOCUMEMI'S YOU DOlNiT NEEDt TOTAL NUMBER OF COPIES REQUIRED:
LTTR 29 ENCL 26
~
~
Pennsylvania Power & Light Company Two North Ninth Street
~ Allentown, PA 18101
~ 215/7706151 NAR 10 1989, Harold W. Keiser Senior Vice President-Nuclear 215i770 4194-h I
hi '
Director of Nuclear Reactor Regulation Attn.:
Dr. W. R. Butler, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION REVISION 6 TO UNIT 1 AND REVISION 3 TO UNIT 2 PUMP AND VALVE ISI PROGRAMS PLA-3165 FILES R41-2/R15-7/A17-16 Docket Nos. 50-387 and 50-388
Dear Dr. Butler:
Attached are Revision 6 to the SSES Unit 1 Pump and Valve Inservice Inspection Program and Revision 3 to the Unit 2 Pump and Valve Inservice Inspection Program.
The following is a description of the changes:
UNIT 1 PUMP AND VALVE ISI PROGRAM Page Number(s) 36 and 40 Descri tion of Chan e
Deletion of SRV function of valves PSV-151 F055A and PSV-151 F055B Justification of Chan e Deletion of RHR Steam Condensing Mode by plant modification DCP iI86-7033 UNIT 2 PUMP AND VALVE ISI PROGRAM
,Page Number (s) 33 and 36 Descri tion of Chan e
Deletion of SRV function of valves PSV-251 F055A and PSV-251 F055B Justification of Chan e
Deletion of RHR Steam Condensing Mode by plant modification DCP i/86-7034 Very truly yours, H. W. Keiser 8903220018 S5'0310 PDR ADOCK 050003S7 9
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)ocnment Control Desk (orlgtnal)~
NRC Region I Mr. M. C. Thadani, NRC Project Manager-Rockville Mr. F. I. Young, NRC Sr. Resident Inspector-SSES
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RESIDVAL HEAT REMOVAL M-151 Sheet 1(Continued)
Valve
- Number, co V Oe V M
M Cl CO 44 )
Cl 0 M 44 CO A
B C
HV-1F027 h 2
D-3 X
Cl Cl OJ Cl 0
o Oe C0 Cl Cl C4 0
0 44 44 Cl 44 M
6 GL M
X 0
m Cl O
44 0
H o
IP o
o g
44 0
Ol 44C 8
Cl Cl Cl
&i 44'6 C,
Q ME Relief Request Req'd No Testing Alternative Remarks ~f ~
C49 HV-1F028 h 2
D-5 X
M X
90 C
Q,MT,LT No 1F031 h 1F031 C
1F046 h 1F046 C
~ HV-1F047 h CHV-1F048 h 0~ HV-1F050 h 2
h-4 2
C-4 2
B-4 2
C-4 X
2 C-5 X
2 D 5 X
1 E-3 X
X 20 C 20 C C
CV 4
C CV 24 GL M
24 C 147 0
Q,ME C
CV,LT.
4 C
20 G M
X ll 0
No No No No Yes 26 CO D
Open test only.
Open test only.
D0 Pressure isolation valve.
~ IP 6
PV-1F051 A 2
C-8 X
6 GL h
N/A C
= HV-1F053 h 2
C-7 PSV-1F055 A 2
-5 X
X X
79 A 2
B-6 X
HV-1F103 A 2
C-4 X
4 GL h
8 RV 1
GL S
X N/h C
Q4ME Yes C
LT,SRV No 3
C Q,MT Yes 1
GL M
X N/A C
LT No 25 CS 38 See Relief Request.
id acting valve.
(a Leak tes in reverse direction.
Og o
oo c m
0 o
co H
Vl l o
O
RESIDUAL HEAT REM)VAL M-151 Sheet 2 (Continued)
Valve Number COC 5 NA o cnMA O
C O CCI V M
Oi CO JJ )
OC 0 M CJ CCJ A
B C
D OJ CJ
)
'N CO JJ CO 0
CO lCI 0
4CN
't4 CO co C0
~J 0
Se OJ$ 4 0 0
CJ JJ O
CO JJ 0
0 JJ n
4 S% M Oc m
CO 0
CJ 0
0 H
CC CO 0
CJJ 4
CO OJm 4C JJ CO CJ'J 4C H 04 Relief Request Req'd Te ing A
ernative Remarks HV-1F050 B 1
E-7 X
X C
CV,LT Yes 2
CS Pressure isolation valve.
PV-1F051 B 2
C-5 X
HV-1F053 B 2
D-4 X
6 GL A
N/h C
Q,MT 4
GL A
N/h Ye 25 CS Yes 25 CS PSV-1F055 B
2 D-4 X
X X
8 RV C
JSR No SV-1F079 B 2
C-2 X
HV-1F103 B 2
C-3 X
1 GL S
X 3
X 1
GL M
X
/h C
LT Yes No 38 See Relief Request.
Rapid acting valve.
Leak test in reverse oo PSV-15106 B
2 PSV-IF097 2
~ HV-1F122 B 1
C-3 X
A-5 X
E-7 X
X 1
RV C
LT No 4
RV C
LT,SRV No 1
h X
3 C
Q,MF,LT Yes 26,38 CS Pressure isolation v
ve.
Rapid acting valve.
PSV-1F126 1
E-7 X
X X
1 RV C
LT No 1F090 B
2 F-5 X
X 2
C 0
CV Yes 24 See Relief Request.
Closure test only.
Xl 0
CO C
0 CJC M
CO C
O