ML18026A342

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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  Talen Energy icon.png
Issue date: 04/16/1981
From: Curtis N
PENNSYLVANIA POWER & LIGHT CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
Shared Package
ML18026A343 List:
References
PLA-742, NUDOCS 8104210464
Download: ML18026A342 (6)


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0 REGULATuR Y ib'FORMATION DISTRIbUT ION SYSTE'l (RIDS DOCKET 05000387 05000388 ACCESSION NiR;810421046Er DOC,'DATE: 81/04/16 NOTAPIZED:

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~ 'UTHuR AFFILIATION CURT I S P N ~ '4 r Pennsylvania Power

& Light Co ~

RECIP ~ NA~E REC IP I h.t'll 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

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DISTRISUTIOI( CODE:

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TITLE:,PSAR/FSAR A4IDTS and Related Correspondence NOTE.S:Sena l&E 3 copies FSAR

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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 Attachment 1 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.

Attachment 2 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.

Attachment 3 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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