View source for 05000336/LER-1997-003, Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised

{{Adams
| number = ML20137Y710
| issue date = 04/15/1997
| title = Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised
| author name = Joshi R
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = 
| docket = 05000336
| license number = 
| contact person = 
| document report number = LER-97-003-ERR, LER-97-3-ERR, NUDOCS 9704230188
| package number = ML20137Y667
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 1
}}
{{LER
| Title = Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000336
| LER year = 2097
| LER number = 3
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:_.                     _           .._m             _ __.    .. _ _ _ . - .. .                       .    ~m        . _ _ _ _ _ _             _                .m. _ _ _
l I
     .'NRC FORM 366                                         U.s. NUCLEAR REGULATORY Commission                             APPROYED BY OMB NO. 3160-0104 EXPtRES 04/30/98 LICENSEE EVENT REPORT (LER)                                                  woe'E U Mr"la" E M O s*""iUn"# E E t'A"No^LM'P."P"^'!%3i, 'E!@~"14"%7ffs'io   5
                                                                                                                                                                        ^WI (See reverse for required number of                                      E"u? Er'fa""n'sSEa'r*oSv"$Es"sfo*u?w"a'sfisSETc digits / Characters for each block)                                  owc' EAuiSelrElloEsY UfsEr*oE!NE'3P" FACILITY NAME (13                                                                                     DOCKET NUMBER (2)                              PAGE (3) l                               Millstone Nuclear Power Station Unit 2                                               05000336                               1OF4 TITLE m HistoricalTechnical Specification Noncompliance of Plant Surveillance Procedure Used to Perform Periodic inspection of Fire Protection System Smoke Detectors EVENT DATE (5)                        LER NUMBER (6)                      REPORT DATE (7)                   oTHER FACILITIES INVOLVED (8)
MONTH        oAY      YEAR      YEAR sE        ^L      "           N MONTH       DAY    YEAR NU               NU         R 12          16       96        97      -- 003 --                01         04        15     97 OPERATING                    THIS REPORT IS SUBMITTED PURSUANT To THE REQUIREMENTS oF 10 CFR 1: (Check one or more) (11)
MODE (9)             5          20.2201(b)                             20.2203(a)(2)(v)               X 50.73(a)(2)D)                      50.73(a)(2)(viii)
POWER                          20.2203(a)(1)                          20.2203(a)(3)D)                   50.73(a)(2)Di)                    50.73(a)(2)(x)
LEVEL (10)          000          20.2203(aH2>0)                         20.2203(a)(3)(ii)                 50.73(a)(2)0ii)                   73.71 20.2203(a)(2)Di)                       20.2203(a)(4)                     50.73(a)(2)0v)                    oTHER 20.2203(aH2)Dii)                       50.36(c)(1)                       50.73(a)(2)(v)               specify in Abstract below 20.2203(a)(2)Uv)                       50.36(c)(2)                        50.73(a)(2)(vii)            in NRC Form 366A LICENSEE CONTACT FoR THIS LER (12)
NAME                                                                                                      TELEPHONE NUMBER pnclude Area Codel R. G. Joshi, MP2 Nuclear Licensing                                                             (860)440-2080 COMPLETE ONE LINE FoR EACH COMPONENT FAILURE DESCRIBED IN THis REPORT (13)
CAUSE         SYSTEM    COMPONENT       MANUFACTURER                                  CAUSE    SYSTEM    COMPONENT        MANUFACTURER O PRDS                                                                               O PRDS sVPPLEMENTAL REPORT EXPECTED (14)                                           EXPECTED                 MONTH            DAY            YEAR YES                                                                                            SuBMISsloN (If yes, complete EXPECTED submission DAT E).                            X No                    DATE (15)
ABSTRACT (Limit to 1400 spaces,i.e., approximately 15 single-spacedtypewnttentines) (16)
On December 16,1996, a discrepancy was discovered in the plant procedure utilized to perform the periodic                                                           ,
inspection of the fire protection system smoke detectors. On January 13,1997, a review of this discrepancy identified                                               I that the surveillance procedure utilized prior to November 1995 (Surveillance Procedure (SP) 2618C, " Fire Protection System Smoke Detector Test") did not ensure that the requirements of Technical Specification (TS) Surveillance Requirement 4.3.3.7.1 were met. In addition, on March 16,1997, it was discovered that SP2618C did not adequately document the trip functions of associated components during the testing of smoke detectors.
Fire protection requirements are no longer contained in the Technical Specifications. These requirements were removed by Millstone Unit No. 2 License Amendment No.191 which was issued on November 3,1995. Prior to Amendment No.191, Technical Specification Surveillance Requirement 4.3.3.7.1 included requirements for smoke detectors in the Auxiliary Building (-5 foot elevation). The requirements for the fire protection equipment were relocated to the Technical Requirements Manual (TRM) which is a plant controlled document.
The cause of both events was failure to properly incorporate Technical Specification surveillance reauirements into                                               j plant surveillance procedures.
This event reports the historical noncompliance with Technical Specification Surveillance Requirement 4.3.3.7.1.
SP2618C has been partially revised to ensure compliance with the fire protection system requirements in the TRM for the smoke detectors.
9704230188 970416 PDR          ADOCK 05000336 S                                PDR
}}

{{LER-Nav}}