View source for W3P87-1096, Responds to Generic Ltr 87-06 Re Measures to Assure Integrity of Pressure Isolation Valves (Pivs) as Independent Barriers for Rcpb.Pivs Separating RCS from Attached Low Pressure Sys Listed in Tech Spec Table 3.4-1

{{Adams
| number = ML20215B883
| issue date = 06/11/1987
| title = Responds to Generic Ltr 87-06 Re Measures to Assure Integrity of Pressure Isolation Valves (Pivs) as Independent Barriers for Rcpb.Pivs Separating RCS from Attached Low Pressure Sys Listed in Tech Spec Table 3.4-1
| author name = Cook K
| author affiliation = LOUISIANA POWER &amp; LIGHT CO., NEW ORLEANS PUBLIC SERVICE CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000382
| license number = 
| contact person = 
| document report number = GL-87-06, GL-87-6, W3P87-1096, NUDOCS 8706170493
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
}}

=Text=
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LOUISIAhA POWER & UGHT COMIENY
      ;;ww -                                          INTER-OFFICE CORRESPONDENCE NEW DRLEANS PUSUC SERVICE INC.
E                                  June 11, 1987 l
l W3PF    96 A4.0 QA                -l 1
U.S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, D.C. 20555                                                           l

==Subject:==
Waterford 3 SES Docket No. 50-382 License No. NPF-38 NRC Generic Letter 87-06 REFERENCEt NRC Generic Letter 86-07, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves, dated-March 13, 1987.
                                                                                          ]
f This reply to.the referenced generic letter provides the information requested regarding measures to assure the integrity of pressure isolation valves (PIVs) as independent barriers for the reactor coolant pressure boundary.                                                                      ,
l Waterford 3 was licensed after 1979. Pressure isolation valves (PIVs)           j separating the reactor coolant system from attached low pressure systems-      J are listed in Technical Specification Table 3.4-1 with the maximum              j permissible leakage rates. The test frequency for PIV's is specified in         !
Technical Specification 4.4.5.2.3.
1 Very truly yours,
                                                          &y/   lhf utSh ,h g
K.W. Cook Nuclear Safety and Regulatory Affairs Manager KWC:GEW:pmb cc:  R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR                                                       j NRC Resident Inspectors Office                                             l' E.L. Blake W.M. Stevenson g6170493870611
   'p     4 DOCK 05000382-                                                             O PDR "AN EQUAL OPPORTUNITY EMPLOYER"                           l
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