ML18040A927

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: ML17156B065 ML17156B067 ML18040A927
References
PLA-3165, NUDOCS 8903220018
Download: ML18040A927 (6)

Text

ACCELERATED DI~BUTION DEMOYSTR+lON SY) TEM 1 iS REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8903220018 DOC.DATE: 89/03/10 NOTARIZED: NO DOCKET N FACIL:50-387 Susctuehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION KEISER,H.W. Pennsylvania Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R.

Inservice Insp Program DISTRIBUTION CODE: A047D TITLE: OR

.~

Office of Nuclear Reactor Regulation, Director (Post 870411

SUBJECT:

Forwards Rev 6 to Unit 1 & Rev 3 to U COPIES RECEIVED:LTR g/j it Submittal: Inservice Inspection/Testa g/Relief from N

2, " ump & Valve ASME Code R

NOTES:LPDR 1 cy Transcripts. 0500038 LPDR 1 cy Transcripts. 05000388 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 LA 1 0 PD1-2 PD 5 5 THADANI,M 1 1

/

INTERNAL: ACRS 6 6 AEOD/DSP/TPAB 1 1 ARM/DAF/LFMB 1 0 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NUDOGS-ABSTRACT 1 1 OGC/HDS2 1 0 R ~ILE Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL EG&G BROWN i B 1 1 EG&G ROCKHOLD i H 1 1 LPDR 1 1 NL 007 HEMMING 1 1 NRC PDR 1 1 NSIC 1 1 NOTES: 2 2 S

/

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, h I

hi Harold W. Keiser Senior Vice President-Nuclear 215i770 4194-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 Docket Nos. 50-387 PLA-3165 FILES R41-2/R15-7/A17-16 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) Descri tion of Chan e Justification of Chan e 36 and 40 Deletion of SRV function Deletion of RHR Steam of valves PSV-151 F055A Condensing Mode by plant and PSV-151 F055B modification DCP iI86-7033 UNIT 2 PUMP AND VALVE ISI PROGRAM

,Page Number (s) Descri tion of Chan e Justification of Chan e 33 and 36 Deletion of SRV function Deletion of RHR Steam of valves PSV-251 F055A Condensing Mode by plant and PSV-251 F055B modification DCP i/86-7034 Very truly yours, H. W. Keiser 8903220018 S5'0310 PDR ADOCK 050003S7 9 PDC Control Desk (orlgtnal)~

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RRRC )ocnment NRC Region I Mr. M. C. Thadani, NRC Project Manager-Rockville Mr. F. I. Young, NRC Sr. Resident Inspector-SSES

P

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<<g<<1 <<<<) I" 'l fg <<y<<l, <<t I Ri<<'

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II li

RESIDVAL HEAT REMOVAL M-151 Sheet 1(Continued)

C 0Cl m Cl 0 O 44 M Cl 0 44 C

C4 0 H o 8 Cl Cl 0 44 44 Cl Cl 44 IP M

44 )

Cl 0 M CO Cl 44 OJ Cl o

o g

co 0 o 44 0 Relief V V

~f Cl Cl Oe CO Oe M Ol &i Valve Request Testing

~

44'6 Number, A B C Req'd Alternative Remarks HV-1F027 h 2 D-3 X 6 GL M X C, Q ME No C49 HV-1F028 h 2 D-5 X M X 90 C Q,MT,LT No 1F031 h 2 h-4 20 C 1F031 C 2 C-4 20 C CO C CV No 1F046 h 2 B-4 4 C CV No Open test only.

D 1F046 C 2 C-4 X 4 C No Open test only.

~ HV-1F047 h 2 C-5 X ll D CHV-1F048 h 2 D 5 X 20 G 24 GL M

M X

147 0

0 0 ~ IP Q,ME No 0

~ HV-1F050 h 1 E-3 X X 24 C C CV,LT. Yes 26 Pressure isolation 6

valve.

PV-1F051 A 2 C-8 X 6 GL h - N/A C Q,MP Yes 25 CS

=

HV-1F053 h 2 C-7 4 GL h N/h C Q4ME Yes 25 CS PSV-1F055 A 2 -5 X X X 8 RV C LT,SRV No 79 A 2 B-6 X 1 GL S X 3 C Q,MT Yes 38 See Relief Request. id acting valve.

(a HV-1F103 A 2 C-4 X 1 GL M X N/A C LT No Leak tes in reverse direction.

Og o o oo c co m

H Vl l 0

o O

RESIDUAL HEAT REM)VAL M-151 Sheet 2 (Continued)

C Oc m

~J 0 CO 0 CJ CO M 0 0 Se 0 OJ CO C OJ$ 4 0 H CC m CJ )

OJ 0 JJ CJ 4C O

5 NA o JJ 0 )

Oi M

CO OC 'N CO 4C 0 CO JJ 0

0 CO JJ cnMA O CJ JJ 0

CO N

't4 JJ n CO 40 Relief CJ'J C O CCI V CCJ CO lCI co CO 4 S% M CJJ H 4C 04 Valve Request Te ing Number A B C D Req'd 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 6 GL A - N/h C Q,MT Ye 25 CS HV-1F053 B 2 D-4 X 4 GL A - N/h Yes 25 CS PSV-1F055 B 2 D-4 X X X 8 RV C JSR No SV-1F079 B 2 C-2 X 1 GL X 3 Relief Request.

S Yes 38 See Rapid acting valve.

HV-1F103 B 2 C-3 X X 1 /h GL M X C LT No Leak test in reverse oo PSV-15106 B 2 C-3 X X 1 RV C LT No PSV-IF097 2 A-5 X 4 RV C LT,SRV No

~ HV-1F122 B 1 E-7 X 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 M CO C CO C

0 CJC O