ML18026A342

Forwards Containment Steam Bypass Calculation,High Pressure Diaphragm Leakage Test & Results of Analysis for Wetwell Spray Termination of Pressure Increase,Per NRC Requests

ML18026A342
Person / Time
Site:	Susquehanna
Issue date:	04/16/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML18026A343	List: ML18026A342 ML18026A344 ML18030A040 ML18030A533
References
PLA-742, NUDOCS 8104210464
Download: ML18026A342 (6)

Text

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I ( ( 0 REGULATuR Y ib'FORMATION DISTRIbUT ION SYSTE'l (RIDS ACCESSION NiR;810421046Er DOC,'DATE: 81/04/16 NOTAPIZED: WO DOCKET FACIL:5 'usquehanna Steam Electric StationP Unit 1r Penn ylva 05000387 AUT ~

CURT I S P

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uSquehanna Pennsylvania Steam AFFILIATION EleCtriC StatiOnr Unit Power & Light Co ~

2P Pen Sylva 05000388 RECIP ~ NA~E REC IP I h.t'l l AFFILIATION YOU<GRLOOOPB.J. Licensing Branch 1 f.

SUBJECT:

For wards containment steam bypass calcual tionrhioh pressure diaphragm '1 eatage test & results of anl aysis for rretwel l spr ay termination of pressure increase<per NRC requests ~

DISTRISUTIOI( CODE: SOOIS COPIES RECEITEDlLTP.

TITLE:,PSAR/FSAR A4IDTS and Related Correspondence

'g E(RCL / SIZE:Q~ ~ ~

NOTE.S:Sena l&E 3 copies FSAR & all 05000387 ILE 3 copies FSAR & all amends, amends'end 05000388 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAIVE LT1R ENCL IO CODE./NAME LTTR ENCL ACTION: A/0 LICENSNG 0 YOUNGBLOODPB 1 0 RUSHBRUOKgil ~ 0 STARKrR ~ 04 1 1 INTERW~L: ACCIO EVAL BR2o 1 1 AUX SYS BR 07 1 1 CHEM E>lG BR Ob 1 1 CONT SYS BR 09 1 1 CORE PERF BR 10 1 1 EFF TR SYS BR12 1 1 EHERG PREP 2? 1 0 EQUIP QUAL BR13 3 3 GEOSC IENCES 14 1 1 HUM FACT ENG trR 1 1 liYD/GEO BR 15 2 I&C SYS BR 16 1 1 I&E OO 3 3 LIC GUID BR 1 1 LIC QUAL BR 1 1 NATL ENG BR 17 1 1 bECH ENG BR 18 1 1 MPA 1 0 IXRC POR 02 1 l OFLD 1 0 GP L1C BR 1 1 POWER SYS BR 19 1 1 PROC/TST REV 20 1 1 QA BR 21 1 1 BR22 1 1 REAC SYS BR- 23 1 1 EG F IL 01 1 1 SIT Ab'AL BR 24 1 1 STRUCT ENG BR25 1 1 SYS INTERAC BR 1 1 EXTERNAL: ACRS 2l 16 16 LPDR 03 1 1 AS I C Ob 1 1 TOTAL NU'0ltsER OF COP IES REL'VIRID: LTTH 57 ENCL 51

l TWO NORTH NINTH STREE T, AL L EN TOWN, PA l 810 I, PHONEs t215) 821 5)51 April 16, 1981 uiI '//~

i...l Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION CONTAINMENT SYSTEMS BRANCH CONCERNS ER 100450 FILE 841-2 PLA-742 contains a Containment Steam Bypass calculation requested by the Containment Systems Branch at the March 9 & 10, 1981 meeting between NRC and PP&L. This calculation assumes an initial wetwell pressure of 30 psig and shows approximately 27 minutes available without operator initiated spray before wetwell pressure reaches 53 psig design pressure. This calculation is conservative as it does not take credit for heat sinks which should be expected to add 10-20 minutes to the 27 minutes calculated. This calculation supports PP&L's position that automatic wetwell spray initiation is not required. addresses the high pressure diaphragm leakage test required by SRP 6.2.1.1.C Appendix I. This conservative calculation shows that the maximum leakage possible during the SSES Structural Integrity. Test was 6.5%.

as compared to the 10% maximum acceptance criteria in the SRP. The pressure during the SSES SIT was 33 psid as compared to a maximum SSES LOCA AP of 23 psid. Based on this analysis, PP&L feels that an additional high pressure test is not required. contains the results of an analysis for Wetwell Spray Termination of Pressure Increase as requested by the Containment Systems Branch.

Very truly yours, N. W. Curtis Vice President-Engineering & Construction-Nuclear TEG/mks Attachments PENNSYLVANIA POWER IL LIGHT COMPANY

8 ATTACHEMENT 1 TO PLA 742

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