View source for 05000285/LER-1976-019, Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage

{{Adams
| number = ML20087K036
| issue date = 10/14/1976
| title = Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage
| author name = Jones W, Mehaffey R, Moyers S
| author affiliation = OMAHA PUBLIC POWER DISTRICT
| addressee name = Howard E
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000285
| license number = 
| contact person = 
| document report number = FC-304-76, LER-76-19-03L, NUDOCS 8403230237
| package number = ML20087K039
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 5
}}
{{LER
| Title = Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000285
| LER year = 2076
| LER number = 19
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
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Q                   LICENSEE EVENT RE@T                                 50_285/76-19 supplement No. 1 CONTHOL ULOCK:l                 l    l     l     l   l    l                            (PLEA 9E PRINT ALL REQUIRED INFORMATION) 1                                6 A E                                           LCINSE NUM0fR                                    vE                    TV E
              @] l n I el F1 cl al il 7 Ob I o I o l-lo Io Io Io I o 1-10 lo l                          lh11      1111Ill Io13I 14     15                                                      25    20                    30     31     32 CAftGOHV           T                                  00Cuti NUMUER                           (VENT DATE                       REPOnT DATE
              @Cotrt l 7 U               L7 l
b6 l      U69 y60                b l5 lo l-l0 l2l815l l110l0 l1 l 7 l 6l 01                                   68       69                     74 l1 l 0 l 1l h l 7l 6l 75                       80 EVENT DESCRIPTION
             @ lDuring unit shutdown for refuelinc main steam safety valves were checked for relief                                                                               l 7 UD                                                                                                                                                              80
              @E lnressure.                     Five of the ten valvec' cetpoints had drifted from Technical Specification l 7 11 9 80 h ltolernnee of plua or minun one percent. The valves will be inspected during the                                                                                   l 7 u9                                                                                                                                                              e0 3E l refueling outace and their operation evaluated. (LER 50-285/76-19 Supplement No. 1) l 7 11 9 60 8I 7 UD                                                                                                                                                                 I mest                                                                          80 1( E        CODE                 COMPONENT CODE                     GUI ER            M     f  U R           VOLATON
             $ lH lB l [!i]
7 00 to                      11 lV l A lL l V l El XI 12      -
17 d43          l0 l2 lh l3 l               l_Y_]
44                  47         48 CAUSE DESCRIPTION DD l Valve relief prensure drifted due to possible cha' ige in environmental condition from                                                                        l 7 ft 9 00 ll lthe settin6 temperature. Engineering Evaluation / Assistance Request Number 76 h9 has 7 n9                                                                              -
l e0 ll lbeen written to investigate the problem.
l FACILifY                                                                    METHOD OF STATUS                % POWER                     OTHER STATUS              DrSCOVERY                       DISCOVERY DEECRIPTON 7 8           9
                           @               10 l0l0l0l               l NA                             l   W           l Relief Pressure Test                                       l 12 13 44    45        46                                                        80 ACimiY          CoditNT
* RELEASED                                  AMOUNT OF ACTMTV H             [2]          OF       RELEASE l NA lyz_J                                                  l       l NA LOCATON OF RELEASE l
7 6           9                    10      11                                          44      45 80 PERSONNEL EXPOSURES                                            -
NUMDER               TYPE        DESCRIPTON DE l0 l o1 ol                  ( ZJ        l nA                                                                                                                    l 7 . 8, 9                  11        12      13                   . .u 80 PERSONNEL INJUR ES                                                                        .
NUMDfA               DESCRIPT ON 810101 ol l NA                                                                                                 .      .
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            /189                     11 12                                  .;                                   .
80 OFFSITE CONSEQUENCES                                           ':
  '         @ lNA                                                             .
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         ~7       89 80 LOSS OR DAMAGE TO FACILITY Tver        otSCnPTON
            @ in 7 89 l NA 10 l
80 PUDLICITY                                                                                                                   ,
1
            @ l NA                                                             9403230237 761014 PDR ADOCK 05000285                                                                               l 7 8s a                            PDR 80 ADDITIONAL FACTORS                                           'J'                                                                         '
            @ l See Attachments 1, 2 and 3.'                                                                                                                                    l 7 0U                                                                                                                                                              30 l
E1 7.cU                                                                                                                                                                 i 00 m             S. M. Moyern/R. F. Me hn f re y                                      .                 402-h26-h011                          .

o o
LER 50-285/76-19 Supplement No. 1
* Page Two A'IfACIDENT NO.1 Safety Analynis           .
Technical Specification Section 2.1.6(3) requires eight of ten safety valves to be operable with the lift settings between 1000 psia and 1050 psia with a tolerance of j; 1.0% of the nominal nameplate setpoint.
The as found settings showed nine of ten safety valves to be operable with lift settings between 1000 psia and 1050 psia. However, five safety valves vere found to have drifted more than the j; 1.0% of nominal nameplate, as tabulated below:
                                  . Safety Valve         Setpoint        As Found MS-275            1050 psia          1042
                                                                                      ~
FE-276            10h0 psia          1065   .
MS-277            1025 psia          10k0 MS-278            1015 psia          1020 MS-279            1050 psia          1048     ,
                    -                 M3-280            1040 psia          1038
                                  . MS-281            1025 psia          1040                     .
NS-282            1015 psia          1013
_                                  MS-291            1000 psia          1022 MS-292          , 1000 psia          1028
              . The basis for th safety analysis is that the valve relief capacity be greater than 4.7 x 10g/b/hr to prevent overpressurization of the steam system at. loss of load conditions from rated power condition of 1h20 MWT although            -
5 of 10 safety valves drifted greater than j; 1.0%, 9 safety valves were available to provide the required flow between 1000 psia and 1050 psia.
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Supplement flo.1 Page Three ATTACIIME:IT NO. 2 Corrective Action The safety valve drift was found during unit :nutdown for refueling. The valves will be inspected durin6 the outage and vill be reset prior to unit power operation. In addition, Engineering Evaluation / Assistance Request Number 76-49 has been written to further investigate the problem.
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ATTACH!ENT NO. 3 I
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i j                                   This is the second failure of the main s' team safety valves - the first i-failure was reported in LER 50-285/76-19 i
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Omaha Public Power District                                                   ..~~
1023 HANNEY a OMAHA. NEDRASNA 68102        8    TELEPHONE S36 4000 AREA CODE 402 October 20, 1976 FC-304-76                                %                  Jf I?icii
:,//-3.d&p6 u,s, Mr. E. Morris Howard U. S. Nuclear Regulatory Commission
                                                                                                    $5 Won %
Region IV                                                                     c4                         @ /.
611 IWan Plaza Drive                                                             - ,/         ,
gj[ . . , -
gj Suite 1000                                                                                    ~    ~ '
Arlington, TX 76012

==Dear Mr. Howard:==

==Reference:==
Fort Calhoun Station Unit No. 1 Docket No. 50-285 In accordance with the Fort Calhoun Station's Technical Specifica-tions, the Omaha Public Power District, as holder of facility operating license DPR 40, submits three copies of the following licensee event supplement report for 50-285/76-19 to satisfy the requirements of Regula-tory Guide 1.16.
Sincerely, fl        *(i[b W.C.fJones Section Manager Operations WCJ/WDD:rge Enclosure                             .
cc:   Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, DC 20555 (3)
Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission                                               -
9 Washington, DC 20555 (30)
Mr. L. C. Shalla SARC Chairman PRC Chairman                                                         '
Fort Calhoun File (2)
}}

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