View source for 05000318/LER-1983-074, Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209

{{Adams
| number = ML20086Q165
| issue date = 02/09/1984
| title = Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr
| author name = Lyons W, Pieringer P, Russell L
| author affiliation = BALTIMORE GAS &amp; ELECTRIC CO.
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000318
| license number = 
| contact person = 
| document report number = LER-83-074-03X, LER-83-74-3X, NUDOCS 8402270455
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000318
| LER year = 2083
| LER number = 74
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:UPDATE REPORT A              '
PREVIOUS REPORT DATE:                    01-19-84
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3 EVENT DESCRIPTION ANO PRO 8ABLE CONSEQUENCES h l 0 l2 ll        Durine normal operarian. the main steam supply valve to the steam                                                                                           l Ml               driven auxiliary feedwater (AFW) numos failed open causine 21 AFW oumn                                                                                      l l0l4ll           to start. To repair the valve. the auto initiate capability for the                                                                                         l l0j5ll           steam driven AFW pumps was defeated (T.S.3.7.1.2). The AFW system was                                                                                       l
      @l               returned to a normal lineup 17.5 hours after being declared inoper=hle.                                                                                     l l0l7ll           The motor driven pump remained operable throughout the event.                                                                                               l
               ,l      Similar events: 50-318/83-35. 83-30                                            83-50.                                                                       l OE                 CODE        SUSC OE                 COMPONE NT CODE                  SUSCObE        SWBC DE lois1 I c I a l @ L,,xJ @ L..zJ @ I v l A l t lv le Ix l @ L,,rJ @ b.. J @
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[I l o_j l      The diaphragm's casing holes were elongated because of insufficient                                                                                         l l1l1ll          torque on some of t e casinn can screws. A new diaphraam was installed                                                                                      l 11l2ll          and properly toraued. The valve was then tested satisfactorily. Unit 2                                                                                      l l1l3ll          maintenance personnel have been instructed on proper actuator mainten-                                                                                     1 1114ll          ance IAW vendor's Tech Manuals.                                                                                                                         =
l STAT S                % POW E R                     OTNEW ST ATUS           OtS C OV EN T                       DISCOVENT DE SCRIPTION lr Il 5. l. W h l 1l 0l 01@l                                  N/A                    l      bjh!             onorator Observatinn
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RELE SEO           RE       E           AMOUNT OF ACTIVITY                                                        LCC ATION OF R ELE ASE l116l         W h W hl                                N/A                           l              l            N/A                                                        l 98U M SE R           TTPE          D E S C AlPTION 1117. l.l0 l 0 l 01@l Zl@l                                                   N/A                                                                                           l NUMSEN                 E S C RIPTIO.4 l, 1l s l l 0 l 0 l 0 l@l                           N/A                                                                                                                    l
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'      l 119 l [2_jhl                                N/A                            9402270455 840209                                                                             l r    . .             '.                                                    PDR ADOCK 05000318                                                                         ..
                                 ' '                                                O                                                                       NRC USE ONLY e.suSE*'oEs'CaiPTiON h l 2 I o ! [N,,,jhl                        N/A                                                                                            l    lllllllllllll r    . .            i.                                                                                                               ..     ..                        ..
NAME OF PREPARER                    P. Pieringer/W. Lyons                                        PHONE: (301) 269-4742/4861

o
/
B ALTIMORE G AS AND ELECTRIC COMPANY P.O. BO X 14 7 5 B A LTIM O R E, M A R Y L A N D 2120 3 NUCLEAR POWER DEPARTMENT cQLVERT CLIFFS NUCLEA R POWER PL ANT LUSBY. M ARYL AND 20657 February 9, 1984 Dr. Thomas E. Murley                                           Docket No. 50-318 Regional Administrator                                         License No. DPR 69 U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406

==Dear Dr. Murley:==

Attached is LER 83-74/3X, Revision 1, as required by 10 CFR 50.73.
Should you have any questions regarding this report, we would be pleased to discuss them with you.
Very truly yours, L
L. B. Russell '
Plant Superintendent LBR:WTL:bsb cc: Director, Office of Management Information and Program Control Messrs:    A. E. Lundvall. Jr.
J. A. Tiernan
                                                                                                #r 4
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}}

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