ML18026A366
| ML18026A366 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/10/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| PLA-834, NUDOCS 8106120170 | |
| Download: ML18026A366 (13) | |
Text
REGULATOP INFORMATION DISTRIBUTION
.TEM (RIDS)
ACCESSION NBR:8106120170 DOC ~ DATE: 81/Ob/10 NOTARIZED:
NO DOCKET' FACIL'.50-387 Susquehanna Steam Electr ic Station<
Unit 1, Pennsylva 50 388 Susquehanna Steam Electric Stationi Unit 2i Pennsylva 05000388 AUTH,,NAME AUTHOR AFFILIATION CURTISiN ~
WE Pennsylvania Power 8 Light Co ~
REC IP ~ NAME RECIPIENT AFFILIATION SCHWENCERiA ~
Licensing Branch 2
SUBJECT:
Forwards response to NRC question on SER Open Item 33 re.
fleshing in ECCS pump suction lines.NPSH for ECCS pumps is adequate to preclude local flashing in suction pip'iqg, DISTRIBUTION CODE:
B001S COPIES RECEIVED:LTR ENCL SIZE ~
TITLE'. PSAR/FSAR AMDTS a'nd Related Correspondence NOTES:Send ILE 3 copies FSAR 8 all amends.l cy:BWR LRG PM(L;,RIB)
Send IS,E 3 copies FSAR 8 all amends,1 cy:BWR-LRG PM(L ~ RIB) 05000387 05000388 RECIPIENT ID CODE/NAME ACTION:-
A/D LICENSNG LIC BR ¹2 LA COPIES LTTR ENCL 1
0 1
0 RECIPIENT COPIES ID CODE/NAME LTTR ENCL LIC BR ¹2 BC 1
0 STARf<gR ~
04 1
INTERNAL: ACCID EVAL BR26 CHEM ENG BR 11 CORE PERF BR 10 EMERG,PREP 22 EMRG PRP LIC 36 FEMA REP DIV 39 HUM FACT ENG 40 ILC SYS BR 16 LIC GUID BR 33 MATL ENG BR 17 MPA OELD POWER SYS BR 19 QA BR 21 REAC SYS BR
?3 SIT ANAL BR 24 EXTERNAL: ACRS 41 NSIC 05 1
1 1
1 1
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0 3
3 1
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1 1
1 1
1 1
1 1
0 0
1 1
1 1
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16 16 1
1 LPDR 03 AUX SYS BR 27 CONT SYS BR 09 EFF TR SYS BR12'MRG PRP DEV 35 EQUIP QUAL BR13 GEOSCIENCES 28 HYD/GEO BR 30 ILE 06 LIC QUAL BR 32 MECH ENG BR 18 NRC PDR 02 OP LIC BR 34
- PROC/TST.REV 20 RAD ESS BR22 01 STRUCT ENG BR25 1
1 1
1 1
1 1
1 3
3 2
2 2
2 3
3 1
1 1
1 1
1 1
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gag 16 1981 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 6
ENCL
4 l
W 4
N ll JE ll
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~~ ')U.
O'PISTIL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: {215) 770-5151 NORMAN W. CURTIS Vice President
~ Engineering 8 Construction-Nuclear 770.5381 June 10, 1981 Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION
RESPONSE
TO NRC QUESTION 211.296 ER 100450 FILE 841-1 PLA-834
Dear Mr. Schwencer:
Attached please find our response to the Commission's question on". SER Open Item 0'33 regarding flashing in the ECCS pump suction lines.
We believe that this response indicates that there is adequate NPSH available to the ECCS pumps to preclude local flashing in the suction piping.
Very truly yours, Vice President-Engineering and Construction-Nuclear Attachment.
sxosxpo i LD E
PENNSYLVANIA POWER 8
LIGHT COMPANY
Se have revisited the suction pipixxg for alX EGGS punps to detenahxe iX nd~uat>>
MPSH $.s available to preclude local flssMag in the p'ape Local flashing csa occur if khe abso1uka pressure ak that pohxc (h~ ) is less than the vapor pressure (h
) of the HuM.in hstat+haca hfic)'vpxx)
The sue&on piping foz'he core spray syskea is bokS.zonta1. f ~ the sxxctiea strainer to the outside of the auppzessioxx pool penatratian azxd tbar~fker it slopes dcnm coat jnuously to the punps ~itboxxt any vertical Mes Therefore keg tbe location outside oK the pene-tration Q1evacioa 658'-I") os the highest point izx the systen.
(Refer to Node "F." of the CS Sp$ p. calculstioas presented as a respoxxse Co SZR Open itexs 33 by lettez PEA-779)
For sizxplicity conservatively assume that all 8.88 feet of. friction loss (hf) is betxaxe x khe suction straixxer inlet aad the first drop right oxxtside oà the suppression pool peaetratioa.
Using khe 5P58h auabers from
.Qutk calcem'.atioa, the available + would 'be:
(620-658.08) + 33.16 - 8.88 ~ 36.2 feet The required pz'essure is the vapor pressure ak 2M Fz bvps~ 2?.6l.
- feet.
Shxce the hap hvpa there ia adequate pressure ak tais pohxk to prevent local flashixxg.
Ttxe remainder of the pipDxg frcnx this point to the pushup does aot go upward, therefore va can conclude that Chere ie no local flashing.
S~harly the succioa piping for the RER system is horizontal froa the suction stxaXnexs to the outside of the suppression pool pexxe-trakion nad thereafter it slopes d~ coatiauoxxsly ko tbe puap tritb-oxxk aay vertica3. rises.
Ther*fore caking the location outsMe of
. cbe penetration (Elevatioa 658 -f") as khe highesc point ia cbe systea.
(Refer Co Bode "C-2" of Che RBR SPSK calcuIatfoaa presented.
aa a response to SKR Open Xtea 33 via letter PLA-779).
5'ar s&cpHcity> conservatively assume that all 6.Z feet of friction Xues Oxf) is betveen the suction strainer inlet sad the first drop tfgat outs&Re of suppression pool peaekkacioxx.
Using the NPSBA nasibera from that cxxlculakioa~ the available ha'uM bez
~ (620-65S.08) + 33.16 - 6.7 38.38 feet The required pressure is the vapor pzessuze ak 200 F:
hvpa~27.6I feet Since the ha') bvpa there is adequate Pressure at thia PoRt.
to prevent local flxxshixxg.
The xeaaiader of the piping froxa this point to che Pxxxap does nok go upvard, therefore ve can coaclud>>
that there is zxo local flashing..
Rosrevex'~ the suckion pipe for the BPCX punp Camas a vertical rise of Sour feat inside khe suppression pool ~ to the elevation of the suppression pool peuekrakioael>>va&oxx 658'<<1" Refer ko the NPSR calcuhCioa presented Xn the PSAR section 6.3.Z.2 ?.2
%'or oW paucity> cons>>rvakively assume Chat all 16 feet of friction loss (hf) Ls between tbe auction strainer inlet and the high point
Qa$ xxg the SPSKl. numbers fred this sect&a the availaMe Q~ weuM be:
he 7~58 08) + 33-X6 - 16 R9.08 feet r~uLt'ed pressure Xs the vapor pressure at 140 P hv >> 6 S feat
.: Mm'.e the '4Cj hvua there is adequate pressure at this Ed.gh poLat to prevent local flashing.
The remainder of the piping frow
-centaiznaeat isolation va?va to the pump does not go u~azd aa4 therefore there is rlo local flas~+ 3; Caaclueiou=
There-Xa adequate gpSR evaiiabla to preclude. Local flashing in. the KcCS suction. piping.
- Please note that PSALM mill be revised to state that ednimmx XI~ter level eLevakiou inside the supprassfou pool is 670 f'eat
V,C
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P
.'NRC W1 RIBUTION FOR PART 50 DOCKE:,MATERIAL (TEMPO RA RY FO R M)
CONTROL NO:
FILE.
FROM: ~nnsylvan~
pwr < Light DATE OF DOC DATE REC'D Allentown, Ba.
6-5-n 6-9-7S N W Curtis LTR TWX XX RPT OTHER TO Mr.
W A Butler ORIG 1 signed CC OTHER SENTNRC PDR SENT LOCAL PDR CLASS UNC LASS ZGGK PROP liNFO INPUT NO CYS REC'D 1
DOCKET NO 0-8 8
DESC R IPTION: Ltr with attachment re our, letters of 4-17-7$, and 4-23-75, provides add. info with regards to the LOCA related suppreksion pool hydrodynamic phenomena...
PLANT NAME:
Susquehana 1 5 2 ENCLOSURES:
AcjgNQ~IEBggg L)0 QT PP)r FOR ACTION/INFORMATION h V1
~ BUTLER (L)
W/copies CLA%K (L)
W/ Copies PARR (L)
W/ Co!ries KNIEL (L)
W/ Copies SCHWENCER (L)
W/ Copies
'TOLZ (L)
W/ Copies VASSALLO (L)
W/ Copies PURPLE (L)
W/ Copies ZIEMANN (L)
W/ Copies DICKER (E)
W/ Copies KNIGHTON (E)
W/ Copies YOUNGBLOOD (E)
W/ Copies REGAN (I=)
W/ Copies LEAR (L)
W/'opies SPIES W/ Copies LPH W/
opies G F I LE TECH REVIEW
~N SCHROED" R
~~GC, ROOM P-506A MACCARY
~~OSSI CK/STAFF I NIGHT
+~'CASE PAWLICKI ip( IAMBUSSO SHAO.
B(.'>YD
~ STELI.O MOORE (L)
HOUSTON
~ DE YOUNG (L)
~MOVAKQ)
SKOVHOLT (L)
/ROSS GO!. LER (L) (Ltr)
IPPOLITO P. COLLINS
~TEDESCO
'ENiSE LONG RFG OPR Q.)
LAINAS FILE & REGION (2)
BENAROYA MIPC VOLLMiER INTERNALDISTRIBUTION A/T IND.
BRAITMAN
'ALTZMAN (L)
MELTZ PLANS
.~CDONALD CHAPMAN DUBE ',I tr)
~E. COUPE PETERSON HARTFIELD (2)
KLECK'ER DEiNTON LIC ASST G R IMES R. DIGGS (L)
GAMIi'IILL H. GEAR IN (L)
KASTNER E, GOULBOURNE BALLARD
-P. KREUTZER (E)
SPANGLER J. LEE (L)
~M. MAIGRET (L)
ENVIRO
~
S. REED (E)
MULLER M. SERVICE (L)
DICKER S. SHEPPARD (L)
KNIGHTON M. SLATER (E)
YOUNGBLOOD H. SMITH (L)
REGAN S. TEETS (L) g PROJECT LDR G. WILI IAMS (E)
'. WILSON (L)
HARLESS R. INGRAM (L)
.lf. DUNCAN EXl ERNAL DISTRIBUTION LOCALPDR 'iikes Barre, ry Tlc. (ABERNATHY)
(1)(2)(10) NATIONALLABS
+ NSIC (BUCHANAN) 1 W. PENNINGTON, Rrn E-201 GT 1 ASLB 1
CONSULTANTS 1 Newton Anc!erson
'NEWMAR K/BLUME/AG8ABIAN g/f ACRS i~-BR@/SENT r0 A8iGJE.T.
pcs 0) 1 PD R-SAN/LA/NY 1 BROOKHAVENNAT LAB 1 G. ULRIKSON ORNL
s~ I O'PBIL
'RetlURtosJ
>ac~et F'~e 0
TWO NORTH NINTH STREET, ALLENTOWN, PA. 1810I PHONEs (2)5) 821-June 5, 1975 Dr. Walter R. Butler, Chief Light Water Reactors Branch 1-2 Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 4lQ@g eall Scc'll 0)
Docket Nos, 50-387 50-388
Dear Dr. Butler:
SUSQUEHANNA SES ADDITIONAL INFORMATION-CONTAINMENTDESIGN QCU ER 100450 FILES 840-2, 170 PLA-69
~rcpt sos'-WE pe 'I>>
'.OII,',asIssss
/
~
t (s
Your letter of April 17, 1975 indicated that the NRC requires o
information relative to the design of the containment for the Susquehanna Steam Electric Station, Units 1 and 2.
You requested that we submit to you within thirty days our program and schedule for prompt resolution of the poten'tial problems associated with the LOCA related suppression pool hydro-dynamic phenomena identified by General Electric during Mark III testing.
Your letter of April 23, 1975 requested additional information related to the effects of main steam relief valve operation.
You requested that we respond within 90 days or that we advise you within 15 days if we cannot meet this schedule.
Subsequently, we informed you that we would submit our proposed program and schedule for resolving these issues the week of June 2, 1975.
Since the investigations of the phenomena discussed in your letters are interrelated, we have chosen to respond to both subjects together.
Prior to receipt of your letters'we had'begun a program to evaluate cer-tain suppression pool phenomena.
These phenomena, as identified in our April 4, 1975 letter to Mr. J.
P. O'Reilly, are:
1.
Suppression Pool Swell 2.
Containment Vent Pipe Horizontal Loads from Steam Condensation.
3.
Main Steam Safety/Relief Valve discharge pipe air clearing.
PENNSYLVANIA POWER 8
LIGHT COMPANY
'I
sa iA A
l t
~ Il e
Page 2
The program to investigate these three phenomena, and the other phenomena mentioned in your letter, is described in the attachment and reflects our long-term approach to resolution of these problems.
The program and schedule were developed in conjunction with General Electric by the" utilities owning plants with Mark II containments.
As part of our near term efforts to permit restart of containment construction, we have done a substantial amount of work in terms of defining bounding loads, based on information supplied by General Electric, and determining the capa-bility of the existing structures.
Based on this work, we have concluded that
.some of the "holds" placed on containment construction activities can be lifted.
Ne have scheduled a meeting for June 17 with the NRC to discuss the bounding
- loads, methods of structural analysis used to determine structural capability, and our plans for the resumption of containment construction.
Very truly yours, N.
W. Curtis Vice President-Engineering 5 Construction CTC:MAS c-Messrs.
Mr. J.
P. O'Reilly - US Nuc.
Reg.
Com.
Director-Region I U.S. Nuclear Regulatory Commission 931 Park Avenue King of Prussia, PA 19406
Q d
1
ATTACHMENT MARK II CONTAINMENT PROGRAM 5 SCHEDULE
~Pro rsm Submit suppression pool and relief valve drawings reflecting current design.
Schedule
- July, 1975 LOCA Questions**
SRV Pi>
~uestion
~*
5*
2.
Submit a generic "Forcing Function Report" which will provide the time history of pool dynamic forcing functions and the methods for relating these functions to the containment structures and components.
Sept.,
1975 2, 7*
1*
2 4*/
3.
Submit a description of suppression pool temperature monitoring system.
(Temperature limits and transients will be described in the Final Safety Analysis Report.)
Oct.,
1975 Not Appl.
7, 8, 9,IQ S.
Submit a preliminary assessment of containment structures and components based on the Forcing Function Report.
Nov., 1975 3, 4, 5, 6, 7*, 8 3
4*
5 S.
Submit a schedule for the generic test program and mathematical models which justify the forcing functions used to assess containment structures and com-ponents.
Dec.,
1975 6.
Submit a schedule for the final assess-ment of containment structures and components.
First Quarter 1976
- Partial Answer Question Numbers correspond to the additional information requests contained in NRC letters dated April 17 and April 23, 1975.
Pr<<I'I K
f>
1 8