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 W PENNSYLVANIA POWER & LIGHT CO.
To:	PARR O D Office of Nuclear Reactor Regulation
References
840-2, NUDOCS 7908150655
Download: ML18031A226 (3)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)RECIPIENT ID CODE/NAME AD C~g LA LulE WH RECIPIENT ID CODE/NAME ACTION'5 PM BC/.ulR'B LTTR EN L I.TTR ENC ACCESSION NBR:7908150655 DOC SEDATE: 79/08/07 NOTARIZED:

NO DOCKET¹FACIL;50 387 Susquehanna Steam Electric Stationg Unit ig Pennsylva 05000387 50-388 Susquehanna

'Steam Electric Stationi Unit 2i Pennsylva 38 AUTH, NAME AUTHOR AFF ILIAT ION 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 pool of Unit 1.Data from test to serve as basis for reduction of both pool boundary 8 submerged structure load specs, DISTRIBUTION CODE: B001B COPIES RECEIVED!LTR g ENCL g SIZE: TITI.E: PSAR/FSAR AMDTS AND RELATED CORRESPONDENCE'e

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COPIES COPIES INTERNAL: 0 06 I 8E 09 GEOSC IEN BR 11 MECH ENG BR 13 MATL ENG BR 16 ANALYSIS BR 18 AUX SYS BR 20 I 8 C SYS BR 22 AD SITE TECH 27 EFFL TRT SYS 29 KIRK'WOOD AD PLANT SYS AD SITE ANLYSIS HYDRO METEOR BR OELD 02 NRC PDR 08 OPERA LIC BR 10 0IAB 12 STRUC ENG BR 15 REAC SYS BR 17 CORE PERF BR 19 CONTAIN SYS 21 PONER SYS,BR 26 ACCDNT ANI.YS 28 RAO ASMT BR AD FOR ENG AD REAC SAFETY DIRECTOR NRR MPA 1 1 1 1 1 1 1 1 1 1 1 0 0 1 0 1 0 EXTERNAL: 03 I.PDR 30 ACRS 1 10 1 00 NSIC 1 4'6'g~L a-dd%~~z/a/.<E~~8 EPB~~<<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'i Lt3PE Director of Nuclear Reactor Regulation U.S.Nuclear Regulatory Cormission Washington, DC 20555 DOCKET NOS.50-387 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)PENNsYLYANIA PowER 8 LIGHT coMPAPY 82.5045<