View source for 05000311/LER-1983-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired

{{Adams
| number = ML20076L323
| issue date = 06/08/1983
| title = Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired
| author name = Frahm R, Zupko J
| author affiliation = PUBLIC SERVICE ELECTRIC &amp; GAS CO. OF NEW JERSEY
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000311
| license number = 
| contact person = 
| document report number = LER-83-023-03L, LER-83-23-3L, NUDOCS 8307190123
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 5
}}
{{LER
| Title = Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000311
| LER year = 2083
| LER number = 23
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
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31                                               L11@               LA_l@                   l"I112i0ih 40      di               42                 43                      44                47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o      l Steam Generator Blowdown Valve 23GB4 was steam cut; due to normal pressure in the steaq y l generator being greater than containment design pressure, a license change to eliminatq
      , 7      l testing of the valve is being considered. Valve 2VC6 liner was found damaged. Investy
      , 3      lgation of routine liner replacement is underway. Finally the failure of 4 air particuq i 4      l late detector backup sample line valves was attributed to insufficient seating pressurg 7-apes Qyiyring initial stroke adjustment, A e ygQ g g,were restroked.                                                                                                             80 status              sPoWER                     oTHER $fATUS k,,,)           DISCOVERY DISCOVERY DESCRIPTION h 1 5 d h l0l0l0l@l AETiviry coSTENT                 "       "
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1                                                 ~
         ,     O PSEG Public Service Electric and Gas Company P.O. Box E Pancocks Bridge, New Jersey 08038 Salem' Generating Station July 11, 1983 Dr. Thomas E. Murley   .
Regional' Administrator USNRC Region 1 631 Park-Avenue King'of Prussia, Pennsylvania                     19406

==Dear Dr..Murley:==

LICENSE NO.-DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 83-023/03L This letter is to correct errors in previously submitted
             . Licensee Event Report 83-023/03L (the report was erroneously dated August 6, 1983). The corrected report is attached.
Sincerely yours, f
7 6,
J. M. Zupko, Jr.
General Manager -
Salem Operations
           ' RF:kls
: CC:' -Distribution The Energy People                                                                     .
poV l          i'                                                                                            95-2169 (20M) 118i

         , Report Number:                  83-023/03L
                        ~
Report Date:-                   06-08           Occurrence Date:                05-27-83                                                                -
         = Facility:/                   -Salem-Generating Station Unit 2 Public Service Electric & Gas. Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
         ' Containment Systems - Containment Type B and C Leak Rate -
        .Out-of-Specification.
This report:was initiated by Incident Report 82-118.
CONDITIONS PRIOR TO OCCURRENCE:                                                                         l Mode 5 - Rx Power 0 5 - Unit Load 0 MWe.                                                                ;
DESCRIPTION OF OCCURRENCE:                                                                              .
                              ~
         .From January 17 to April 18, 1983, during a scheduled refueling, routine surveillance of Containment Type B and C components. revealed 7 containment isolation valves with leakage rates greater than the
        . maximum range of the leak rate test equipment (20,000 acem).                      The                   i components involved were Containment Isolation Valves 23GB4, 2VC5, 2VC6, 2VC9, 2VC10, 2VC13, and 2VC14. Since actual. leakage due to each                                  l valve could.not be ascertained, it was not possible to demonstrate                                      !
that the total Type B and'C leakage uas less than 0.60 La as required 4
by Technical Specifications Limiting Condition for Oper ation 3.6.1.2b
          .(applicable only in Modes 1 through 4).
The integrity of the steam generator. tubes was maintained during
       - previous operation providing a redundant barrier to Steam Generator Blowdown Valve 23GB4. Valves 2VC5 and 2VC6 are tested together since
        .no isolation capability exists to allow separate testing.-
Investigation revealed that the leakage was, in fact, past. Valve 2VC5,
       -with Valve-2VC6 providing a-redundant boundary. The remaining valves were in the backup' sampling lines'for the Containment air particulate
         -detector-(APD). The_-Technical Specifications had previously exempted these valves;from leak-rate' testing since they are normally closed-and
          . operated only on an intermittant basis.
All valves) involved.in the occurrence were' repaired and satisfactorily.
.         tested; combined Type-B and C leakage was determined to be within
       ' specification prior to returning to Mode 4 operation.
APPARENT CAUSE OF OCCURRENCE:
4 Disassembly ~of Steam Generator Blowdown Va'lve 23GB4 reveale9 that the valve seating. surfaces ~were damaged by steam cutting. As-noted, investigation-revealed-leakage past Valve 2VC5; an inspection of the 1 valve showed degradation'of.the rubber valve liner. 1No degradation t
was found in the case of Valve 2VC6.                 Reduced life of-the linera has been.noted:and.the. manufacturer has' suggested-replacing them on a
         ' routine basis.
   . -     + ,      . a-.   - _ . ~ - -         = -     -- -. - . -    -   .   .. ....- - a . = - - , ,  -- .

  -LER 83-023/03L                      , APPARENT CAUSE OF OCCURRENCE: (cont'd)
The APD sample line isolation valves tested satisfactorily following stroking of the valves.. As noted, the Technical Specifications
  .oxempted the valves from leak rate testing. The valves had recently been added to the procedure,-and were tested this refueling for the first: time since plant startup. It was assumed that the original otroke adjustment of the valves did not provide adequate force to maintain-seating'of the valves with normal wear of the seat and reduction in actuator spring tension.
ANALYSIS OF OCCURRENCE:
The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the cccident analyses at the peak accident pressure of 47 psig.
Action Statement 3.6.1.2 requires:
With either the measured overall integrated containment leakage rate exceeding 0.75 La, or with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System (RCS) temperature above 200 F.
Leakage rate limits during performance of periodic tests incorporate conservatism to account for possible degradation of the leakage barriers between testing. The combined leakage rate had previously been demonstrated within specification during leak rate testing in 1980-81. As noted, the valves were repaired and total leakage was demonstrated to be within specification during the recent testing.
Due to the loss of redundancy in containment barriers, the event constituted operation in a degraded mode permitted by a limiting condition for operation. The occurence is reportable in accordance with Technical Specification 6.9.1.9b.
CORRECTIVE ACTION:
Valve 23GB4 was reworked and satisfactorily tested. Problems with steam cutting in the Type GB4 valves have previously been noted in Salem Unit 1 (see Unit 1 LER 83-010/03L). Investigation of the problem is underway. In view of the fact that the steam generator would be at a higher pressure than the 47 psig design pressure of the Containment System, consideration is being given to submitting a license change to delete the requirement for testing the valves.
The rubber liners on Valves 2VC5 and 2VC6 were replaced. Based on the recommendations of the manufacturer, investigation of routine replacement of the liners is in progress. As noted, Valves 2VC9, 2VC10, 2VC13 and 2VC14 were restroked and satisfactorily tested.
Following repair of all valves with excessive leakage, final results of Type B and C leak rate testing demonst.ated combined-leakage was within specification.
L

,     LER'83-023/03L                     , FAILURE DAIA:
Masoneilan International, Inc.
    '3/4 inch Control Valve Model 38-20571
    - Masoneilan International, Inc.
10 inch Control-Valve Type 69-32200
    . Prepared By   R.'Frahm                '       N       V
(/     Genen'1 4 Man'ager -
Salem Operations SORC Meeting No. 89-077 e
[          f        -
* P        N        9 e          T ?   T
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