ML18031A226

Advises That SRI Intl Has Begun Work on Planned Safety Relief Valve Bubble Load Test to Be Run in Suppression Pool of Unit 1.Data from Test to Serve as Basis for Reduction of Both Pool Boundary & Submerged Structure Load Specs

ML18031A226
Person / Time
Site:	Susquehanna
Issue date:	08/07/1979
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Parr O Office of Nuclear Reactor Regulation
References
840-2, NUDOCS 7908150655
Download: ML18031A226 (3)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

SEDATE:

ACCESSION NBR:7908150655 DOC 79/08/07 NOTARIZED: NO DOCKET ¹ FACIL;50 387 Susquehanna Steam Electric Stationg Unit ig Pennsylva 05000387 50-388 Susquehanna 'Steam Electric Stationi Unit 2i Pennsylva 38 AUTH, NAME AUTHOR AFF ILIATION CURTIS' < ~ ~ Pennsylvania Po~er 8 I ight Co ~

REC IP, NAME RECIPIENT AFFILIATION PARRgO ~ DE Light (<ater Reactors Branch 3

SUBJECT:

Advises that SRI Intl has begun work on planned safety/

relief valve buoble load test to be run in suppression reduction pool of Unit 1.Data from test to serve as basis for of both pool boundary 8 submerged structure load specs, DISTRIBUTION CODE: B001B COPIES RECEIVED!LTR g ENCL g SIZE:

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR EN L ID CODE/NAME I.TTR ENC ACTION'5 PM AD C~g BC /.ulR'B LA LulE WH INTERNAL: 0 02 NRC PDR 1 06 I 8E 08 OPERA LIC BR 1 09 GEOSC IEN BR 10 0IAB 1 11 MECH ENG BR 12 STRUC ENG BR 1 13 MATL ENG BR 15 REAC SYS BR 1 16 ANALYSIS BR 17 CORE PERF BR 1 18 AUX SYS BR 19 CONTAIN SYS 1 20 I 8 C SYS BR 21 PONER SYS,BR 1 22 AD SITE TECH 26 ACCDNT ANI.YS 1 27 EFFL TRT SYS 28 RAO ASMT BR 1 29 KIRK'WOOD AD FOR ENG 1 0 AD PLANT SYS AD REAC SAFETY 0 AD SITE ANLYSIS DIRECTOR NRR 1 0 HYDRO METEOR BR MPA 1 0 OELD 00 NSIC EXTERNAL: 03 I.PDR 30 ACRS 1

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TOTAL iV~'MBER OF COPIES REQUIRED: LTTR ~ ENCL

TWO NORTH NINTH STREET, ALLENTOWN, PA. 18lol PHONEME t2IS) 821-SIS'I August 7, 1979 KM5tKN MNH O'iLt3PE Director of Nuclear Reactor Regulation DOCKET NOS.

U. S. Nuclear Regulatory Cormission 50-387 Washington, DC 20555 50-388 ATTN: Mr. Olan D. Parr, Chief Light Water Reactors Branch No. 3 SUSQUEHANNA STEAM ELECTRIC STATION SRV BUBBLE LOAD TESTS ER 100450 PILE 172, 840-2 PLA-388

Dear Mr. Parr:

SRI International has recently begun work. on a planned safety/relief valve (SRV) bubble load test to be run in the Unit Il suppression pool at the Susquehanna SES. The scope of the tests will be to, investigate the actual pool loadings associated with SRV discharge using a simulated bubble source. Data from these tests would serve as a basis for a reduction of both the pool boundary and sub-merged structures load specification due to SRV discharge, should such further load reduction be required.

Final verification that the simulated bubble source will give adequate duplication of a SRV discharge pressure-time history is yet to be completed. Should this source not be able to simulate such a pressure-time history, plans for this test will have to be modified or possibly cancelled. Should final verification be completed as planned, testing at the Susquehanna site would take place during the fourth quarter of this year. At the present time instrumentation installation is proceeding.

Should you or the staff require any further information, we will be glad to meet with you to discuss in more detail the test plans.

Very truly yours, N. W. Curtis Vice President Engineering a Construction DFR:dah cc-R. M. Gallo - NRC (sjt:e)

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