ML18030A350
| ML18030A350 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/17/1981 |
| From: | Calhoun J PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0803, RTR-NUREG-803 GL-81-35, PLA-928, NUDOCS 8109280481 | |
| Download: ML18030A350 (3) | |
Text
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RKGULATORY INFORMATION DISTRIBUTION SYSTEM (RIOS) 8109280481
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DOC ~ OATENl /09/17 NOTARIZED'" YES LOCKE!T' Susquehanna Steam Electr i c Stati one Un) t 1<
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-7 Susquehanna Steam Electric Station~
Unit 2'~ Pennsylva 0500 AUTHOR AFFILIATION Pennsylvania Power E Light Co ~
RECIPIKNl AFFILIATION LR censing. Branch 2
SI ZK'UBJECT!'dvises that util has conducted initial review of NURKG 0803 trans~~itted by Generic Ltr. 81 35 re pipe breaks 8 will comply with guidance, items listed. in table 5.1.Coxprehensivel olant soec{fic response will oe submitted by 811229.
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PPaL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEME l215) 770-5151 JACK R. CALHOUN Sr. Vice Presiderst-Nuclear I215) 770.4194
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i' September 17, 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 REVIEW OF NUREG 0803 ER 100450 FILE 841-2 PLA-928
Dear Mr. Schwencer:
PP&L has conducted an initial review of NUREG-0803 "Safety Concerns Associated with Pipe Breaks in the BWR Scram System" transmitted by Generic Letter No. 81-35 on August 31, 1981.
Based on this review, we conclude that we will comply with the guidance items listed in Table 5.1 of the NUREG.
In general, PP&L will perform In-Service Inspection (ISI) for all ASME Section III code components in the SDV subsystem in accordance with ASME Section XI class 2 requirements.
In addition, verification and inspection activities will be performed in the areas of seismic design and SDV piping and supports.
PP&L will begin an equipment qualification/verification effort for components necessary for detection and mitigation of the potential pipe break in the scram system.
We will review and revise, as necessary, the maintenance and operating procedures associated with the SDV and the potential pipe break in the scram system.
The capability for feedwater and condensate system operation independent of the reactor building environment will be verified.
Finally, PP&L will evaluate coolant iodine concentrations to assure that reactor building access is feasible and that 10CFR100 offsite dose guidelines are not exceeded following a pipe break in the scram system.
'P)ot 5
(lo PENNSYLVANIA POWER EL LIGHT COMPANY
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81092S048 pgP00387 PDR gDQCN pDR A
Mr. A. Schwencer Page 2
September 17, 1981 PLA-928 A comprehensive plant-specific response to NUREG&803 will be submitted by December 29, 1981.
V ry ruly yours, Jac R. Calhoun S
ior Vice President-Nuclear Sworn to and subscribed before me this 5I
'r September, 1981 Notary Pb lic JOHN P. MILLER, JR.,
Iary Publi Allentown, t.ough Coun MyCommhsl~ Rqkres May25,1985 WEB/mks cc:
R.
M. Stark - USNRC