ML18030A349
| ML18030A349 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/14/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0803, RTR-NUREG-803 PLA-925, NUDOCS 8109210064 | |
| Download: ML18030A349 (2) | |
Text
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REGULATORY INFOR'4IATION DISTRIBUTION SYSTEv1 (RIDS) 8109210064 DOC ~ DATc.: 81/09/14 NOTARIZED:
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DOCKE.T Susquehanna Steam Electric Stationr Unit 1< Pen~sylva 050 Susquehanna Steam Electric Station~
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SUBJ" CT: Advises that-util will comely w/Table 5.1 of NUREG 0803'Safety Concerns Associated w/Pioe Breaks in BWR Scrani Sys."
Inservice inso ~ill oe conducted for all ASIDE Section III code co~oonents in scram discharge vol subsys.
DISTSISUTIDN CODE:
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Pennsylvania Power 8 Light Company Two North Ninth Street
~ Allentown, PA 18101
~ 215/770515t Norman W. Curtis Vice President-Engineering
& Construction-Nuciear 21 5 / 770-5381 September 14, 1981
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q~) I 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&803 ER 100450 FILE 841-2 PLA"925
Dear Mr. Schwencer:
PP&L has conducted an initial review of NUREG&803 "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.
A comprehensive plant-specific response to NUREG-0803 will be submitted by December 29, 1981.
Very truly yours, N.
W. Curtis Vice President-Engineering
& Construction-Nuclear WEB/mks cc:
R.