ML20246N265: Difference between revisions

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#REDIRECT [[3F0889-15, Responds to Violations Noted in Insp Rept 50-302/89-15. Corrective Actions:Electrolyte Level in Affected Cells Reduced & Work Request Written & Performed to Correct RCS Leakage]]
| number = ML20246N265
| issue date = 08/31/1989
| title = Responds to Violations Noted in Insp Rept 50-302/89-15. Corrective Actions:Electrolyte Level in Affected Cells Reduced & Work Request Written & Performed to Correct RCS Leakage
| author name = Widell R
| author affiliation = FLORIDA POWER CORP.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number =
| contact person =
| document report number = 3F0889-15, 3F889-15, NUDOCS 8909080073
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 5
}}
 
=Text=
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Power C OR P O R AT ION August 31, 1989 3F0889-15 U.'S. Nuclear Regulatory h 4== ion Attention: W= ant Control Desk Washington, D. C.      20555
 
==Subject:==
Crystal River Unit 3 Docket No. 50-302 Operating License DPR-72 Inspection Report 89-15
 
==Dear Sir:==
 
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                                          . Florida Power Corporation (FPC) provides the attached as our response to the subject Ins,mction Report.
Should there be any questions, please contact this office.                                        !
Yours very truly,                                                                                  i Rolf C. Widell Director, Nuclear Operations Site Support                                                          ;
                                                                                                                                              )
WIR: mag Att.                                                                      4 j
xc: Regional Administrator, Region II Senior Resident Inspector i
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                                                                                                                              \
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                                                . POST OFFICE BOX 219
* CRYSTAL RIVER, FLORIDA 326294219 * (904) 7954486
                                                                        . A Florida Progress Company
- _ _ _ _ _ _ .                _._                            _                                                                              b
 
                        ~
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!                                                      FINIDA ECHER (IIGCEATICN                              {
IH5FEC1'ICH REEUU 89-15                              l REEYX 10 NXIG OF VIRKITCN 1
VIDIATICH 69-15-01                                                                  i A. Technical Specification (Li 3.8.2.3 requires that the "A" ard "B" Station    j Batteries be operable during power operation. Surveillance requirement      q 4.8.2.3.2.b.3 specifies that for a battery to be considered operable, the    I electrolyte level of each u4ust.ed cell rust be between the minimum ani      )
                                = vim = level indication marks.                                                '
Ocatrary to the above, an . Tune 21, 1989, with the plant operating at power, several cells of the "A"    Station Battery and Several cells of the "B" Station Battery were observed to have electrolyte levels greater than the maximum level mark which rerdered both statian batteries inoperable.
This is a Seve ny Level IV Violation (Supplement I).                          I l
R$KNSS Florida Power Corporation accepts the violation as stated.      This violation has been reported in accordanoc with 10 CFR 50.73 as IER 89-24.
APPAMNP (MSE OF VIOIATJgf The battery electrolyte level problem resulted frun filling the batteries to just belw the high level scr:be mark during the performance of the battery surveillance p h. ard the batteries then beirg subjected to a significant discharge and recharge cycle. This caused the electrolyte level to exceed the prescribed = vim = mark.
f.UOCA nVE ACTICH The electrolyte level in the affected cells of the Station "A" and "B" batteries was r
* W to within the Technical Specification maximum level mark.
DATE OF FUIL CIMPIJANCE The Station "A" ard "B" batteries were in oaqpliance with the Technical Specification electrolyte limits by June 21, 1989, the same day the violation was discovered.
hTIONS TAYJN 10 PREVfNP Ktunoc2CE The "A" ard "B" Station Batteries mvinn electrolyte level mark has been changed to 1/4" above the existirg high level scribe mark on each battery cell.
The Ergineeriry Staff established this revised maximum level mark based on the manufacturer's statements that tha batteries will function properly as long as the electrolyte does not overflow the batteries.      The 1/4" additional margin provides for at least 1/4" before the cell would overflow.
7he battery manufacturers have stated that the former limit was not consistent with normal battery fluctuations, specifically in regard to increases in electrolyte level due to normal gas generation after a discharge / recharge cycle.
 
j            .
ACTIGE WGN TO PREVDrP T<twxHtNCE (Cont'd)
Therefore, to account for the normal battery cell expansion and due to the fact that the battery manufacturers have agreed that the operability of the battery is not impacted by these charges, labels have been applied to the sides of each battery cell defining the " maximum" level to be 7/30" above the existing
: i.                              manufacturer's scribed high level mark. This mark will be conservative since 7/30" is slightly lcwer than the 1/4" the battery manufacturers have suggested.
7his activity was completed by August 17, 1989 and the weekly Surveillance Procedures were changed to reflect the adjustment. Additional Surveillance Procedures impacted by this change will be corrected prior to the next procedure performance.
l                                Maintenance practices will not be inpacted by these changes, with the exception of the level correction factors that will be adjusted to account for the possibility of electrolyte levels being higher than the scribed high level mark. The manufacturer's high level scribe mark will remain as the upper limit for normal level control of the battery cell.
VIDIATIQi 89-15-02 B.            TS 6.8.1 requires the implementation of written procedures for those activities rm - erded in Appendix "A" of Regulatory Guide 1.33, November 1972, and for implementation of the Fire Protection Program.
Regulatory Guide 1.33, Appendix "A", Section 1.3.d rm -erds procedures for the repair or replacement of reactor coolant pump seals.
Maintenarre Procedur? P2-165, Reactor Coolant Pump Seal Cartridge Renoval ard Replacement, step 7.2.24 requires that the adjustirg cap of the seal be positioned against the pump half coupling.
Administrative Instruction AI-2205, Administration of CR-3 Fire Brigade Organization, Section 4.3, requires in part that the Fire Brigade Team be m M of four qualified Fire Brigade Team members.
Contrary.to the above:
: 1.          On June 10,1989, step 7.2.24 of procedure MP-165 was signed off as completed even though this step had not been performed.                              Not performing this step resulted in emive leakage from a reactor coolant pump seal durirg a fill and vent of the reactor coolant system.
: 2.          On June 18, 20, and 22, one of the four personnel assigned duty as a Fire Brigade Team member was not qualified.
                                                            'Ihis 1s a Severity level IV Violation (Supplement I) .
i____________. _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ - - . _ .
 
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                                                ~
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L                              7 RESP 0 LEE Florida Power Corporation (FPC) aooepts the violation. However, during the investigation for our response to procedure MP-165, it was determined that step 7.2.24 had been performed. A violation did occur because the functions of the step were not parformed in sequence, not because the step had not been l                                                        perform:ri as stated in the violation.
l APPARENP CNUSE OF VIOIATION
: 1)  We excessive leakage from a reactor coolant pump seal during a fill and vent of the reactor coolant system was caused by procedure step 7.2.24 not complying with human factors principles. It contained three different l                                                              fractions instead of one function per step. W ese functions needed to be L
performed sequentially but this was not done.        'Ihis caused the shaft sleeve ' to be lowered and the rotatire faces no larger contacted the stationary faces, thus allowing a flow of reactor coolant between them.
: 2)  he assignment of an unqualified person to the Fire Brigade was caused by the use of an outdated personnel roster.
(nocx;nVE ACTION
: 1)    A work request was written and performed to correct the immediate cancern of the RCS leakage.
: 2)  The individual was removed frun Fire Brigade duty until sume:c:ful l                                                              completion of Fire Brigade requalification.
A Control Room Order was issued to Nuclear Shift Supervisors and Assistant Nuclear Shift Supervisors (FPC's Fire Team Inaders) to make them aware of the violation and how to prevent rectutw.e of the violation.
IRTE OF FUIL CDMPIJANCE
: 1)  Full compliance was achieved on June 12, 1989 upon caqpletion of the work request.
: 2)  Full compliance was achieved on June 22, 1989 when the unqualified Fire Brigade member was replaced with a qualified Fire Brigade membar.
ACTICN 'IAKIN 'IO PREVIWP RDCURRENCE
: 1)  Step 7.2.24 of MP-165 will be separated into three individual sequential steps to prevent the step function frcxn being completed in the wrong sequence. This pivc.clure charge will be made prior to MP-165's next use.
Maintenance pet-el willAe informed of this violation and be cautioned of potential inadequacies of procedural steps that list more than one function. 'Ihese sucxdural inadequacies will be wuucted during the biannual review of the procedures.
 
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ACTIGi TMEN 'IO PREMNT REK1RRENT (Otnt'd)
: 2)                                  A current Fire Brigade member roster will' be sent each . week directly to the printer outside the Control Room. 'Ihis list will be utilized by the Fire Team iswbn- in preparing the list of Fire Team members for his shift.
In addition, eadt Shift Supervisor on Duty and Assistant Nuclear Shift Supervisor will be able to obtain e e w cy team qualification information directly frun the Nuclear Operations Training Information System (NOTIS).
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