IR 05000346/1998011

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Revised Pages 15 & 18 to Insp Rept 50-346/98-11,correcting Number Given for Unresolved Item 50-346/95009-02.Number Should Read 50-346/96002-09
ML20151V601
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 09/09/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20151V593 List:
References
50-346-98-11, NUDOCS 9809150030
Download: ML20151V601 (2)


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the PCAQR directed that drawings reflect nominal tank capacity. This SE justified changes made in support of PCAOR 96-047 The change in quench tank capacity listed in the USAR as 800 cubic feet (approximately 6000 gallons) to reflect a nominal volume of 6700 gallons had no effect on the ability of the quench tank to perform its design function as no change was made to water levels maintained in the tank. The reactor coolant drain tank change in tank capacity listed in the USAR from a usable volume of 655 gallons to a nominal volume of 690 gallons did not affect the tank's ability to

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collect water from plant drains. No change was made to the water level in the tank which was automatically maintained. The team concurred with the licensee's determination that a change to the indicated capacities of the quench tank and primary drain tank did not result in an unreviewed safety questio .

SE 98-0007, "Cooldown Following a Seismic Event / Steam Generators Fed with Service Water, Solids Accumulation in the Steam Generators." PCAQR 96-1290 identified a discrepancy in the USAR concerning the quantity of dissolved and suspended solids that would be accumulated in the steam generators after injecting raw water for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The USAR listed the quantity of accumulated solids over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as less than two pounds. The licensee's reanalysis

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indicates that raw water feed to the steam generators would result in the

_j accumulation of approximately 240 pounds of solids in each steam generator in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The team agreed with the licensee's evaluation that changing the USAR to reflect more accurate solids accumulation in the steam generators did not constitute an unreviewed safety question and did not reduce any margin of safet Conclusion

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Based upon review of selected 10 CFR 50.59 screening documents and safety evaluations, the team concluded that performance in this area was good. The screenings and evaluations were thorough and accurately reflected the licensee's methodology for assuring deviatioris from design, as defined in the USAR did not impact plant safet E8 Miscellaneous Engineering issues (37550)

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E (Closed) Unresolved item (50-346/96002-09k This item was opened for not having appropriate acceptance criteria for determining the condition of emergency lighting batteriec following 8-hour surveillance discharge testing. An acceptance criteria of 5.25 volts was established and current surveillance data demonstrated a low battery failure rate. This item is considered close E8.2 (Closed) Insoection Follow-Uo item 50-346/97201-09: This item was opened to follow resolution of inconsistencies between various documents for the borated water storage tank setpoint. Inspection report 50-346/98003(DRS) documented that the 9809150030 980909

{DR ADOCK 05000346 PDR 15 IEVISED 9/9/98

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! INSPECTION PROCEDURES USED

, IP 37500 Engineering

IP 4000 Effectiveness of Licensee Controls in identifying, Resolving and Preventing Problems IP 37001 10 CFR 50.59 Safety Evaluation Program i

ITEMS CLOSED CLOSED 50-346/96002-09 URI Potential inadequate battery acceptance for emergency light test

! 50-346/97201-09 IFl Several inconsistencies between documents for BWST setpoint  !

LIST OF ACRONYMS USED

EDG Emergency Diesel Generator

IFl Inspection Follow-up Item j ISE Independent Safety Evaluation i

LER Licensee Event Report QA Quality Assurance RCP Reactor Coolant Pump SE Safety Evaluations PCAQRs Potential Conditions Adverse to Quality Reports URI Unresolved item USAR Updated Safety Analysis Report

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REVISED 9/9/98