View source for RBG-26300, Forwards Editorial Correction to 870310 Tech Spec Section 4.6.1.3.f,Page 3/4 6-5

{{Adams
| number = ML20236C310
| issue date = 07/23/1987
| title = Forwards Editorial Correction to 870310 Tech Spec Section 4.6.1.3.f,Page 3/4 6-5
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-26300, TAC-65129, NUDOCS 8707300008
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| project = TAC:65129
| stage = Other
}}

=Text=
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RIVER BEko STATION <      POST OFFICE BOX 220 ,   $7 FRANCISVILLE, LOUISIANA 70775 j,(                                                                                          - ARJ CODE 6N -      635 6.W4      346 8661
.6' July 2?, 1987 RBG -'26300 File Nos. G9.5, G9.25.1.4 i
U.S. Nuclear Regulatory Commission-Document Control Desk Washington, D.C. :20555

==Dear Sir:==
                                                                                                   ' River'. Bend' Station - Unit 1-                      m Docket'No.-50-458-
                                                                     -r Gulf' States / Utilities . Company:.(GSU) is providing the attached-editorial.
correction'to its March 10,1987 ' letter. ' A reference and . justification for                                                          l the addition of the asterisk to< Technical Specification Section 4.6.1.3.f.
                                                   . Page'3/4 6-5 pas provided~1n~thW March 10,.1987 submittal, Attachment 4.-                                                                l 1
Ifiadditional k formation is required, please contact Mr. Rick J.                                         King at (504) 381-4146-Sincerely,                                                             i of          <<~       %-
                                                                                                                     .J. E. Booker                                                            !
Manager-River Eend Oversight                                           ;
River Bend Nuclear Group                                             '!
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                                                                  +                     .-           t                      i Mr. Robert.D. Martin, Regional' Administrator'                                                                                   !
                  ,                                          U.S.' Nuclear Regulatory Commission Region IV' 611lRyan Plaza Drive, Suite.1000
                                                           ' Arlington,.TX' 76011            -
NRC-Resident Inspector'                                                       .
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P.0L Box 1051                                                                   L      )
                                                         .'St.:Francisvil's, LA- 70775
             ' B707300008            ADOCK 05000458; 870723 J$
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: b. If any periodic Type A test fails to meet 0.75 La, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.      If two consecutive Type A tests fail to meet 0.75 La, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed.
: c. Tk accuracy of each Type A test shall be verified by a supplemental test which:
: 1. Con)irms the accuracy of the test by verifying that the differ-ence between the supplemental test data and the Type A test data is within 0.25 La. The formula to be used is: [Lo + Lam
                              - 0.25 La] 1 Lc 1 [Lo + Lam + 0.25 La] where Lc = supplemental test results; Lo = superimposed leakage; Lam = measured Type A leakage.
: 2. Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
: 3. Requires the quantity of gas, injected into the . primary containment or bled from the primary containment during the supplemental test, to be netween 0.75 La and 1.25 La.
: d. Type B and C tests shall be conducted with qas at Pa, 7.6 psig*, at intervals no greater than 24 months * *except for tests involving:            l
: 1. Air locks,                        .
: 2. Main steam positive leakage control system (MS-PLCS) valves and PVLCS valves,
: 3. Penetrations using continuous leakage monitoring systems,
: 4. Primary containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, and
: 5. Purgs supply and exhaust isolation valves with resilient material seals.
: e. Air locks shall be tested and demonstrated OPERA 0LE per Surveillance Requirement 4.6.1.4.
I
: f. Total sealing air leakage into the primary containment, at a test                !
pressure of 11.5 psid for MS-PLCS valves and 33 psid for penetration             l 1eakage control system sealed valves, shall be determined by test at             !
least once per 18 months."*This leakage may be excluded when determin-       !
l ing the combined leakage rate, 0.6 La.                                           '
                            .                                                                           I i
             "Unless a hydrostatic test is required per Table 3.6.4-1.
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