ML20213F065

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Responds to 841024 Memo Re Interpretation of 10CFR50.72 Requirements for Reporting Safety Relief Valve Situations. Valves Not Serving Automatic Depressurization Sys Function That Lift & Reseat W/O Valid Actuation Signal Reportable
ML20213F065
Person / Time
Issue date: 11/16/1984
From: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Norelius C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20213E720 List:
References
FOIA-86-729 NUDOCS 8411210349
Download: ML20213F065 (2)


Text

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F o UNITED STATES NUCLEAR REGULATORY COMMISSION -

gg 3 3 ,I WASHINGTON, D. C. 20555

  • s' k ... 98 NOV 161984 MEMORANDUM FOR: Charles E. Norelius, Director Division of Reactor Projects Region III -

. FROM: Edward L. Jordan, Director -

. Division of Emergency Preparedness and Engineering Response Office of Inspection and, Enforcement

SUBJECT:

INTERPRETATION OF 10 CFR 50.72 REQUIREMENTS C0!!CERNING SAFETY RELIEF VALVES i

This responds to your memorandum dated October 24, 1984, regarding the .

reportability of safety relief valves lifting and reseating. -

You requested that we determine if the following two' situations are reportable under 10 CFR 50.72 and, if so, under which criterion:

1. A safety relief valve thu does not serve an automatic depressurization system (ADS) function lifts an,d reseats in the absence of a valid actuation signal.

2 AnADSvalveliftsandreseatswithout5validen'gineeredsafetyfeature

.- (ESF)actuationsignal.

The first situation is reportable under 1.0 CFR 50.72(b)(1)(fi), which requires the licensee.to notify the NRC Operations Center for:

Any event or condition during operation that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded....

Anytime a safety relief valve spuriously opens there is an unisolable degradat. ion of the reactor coolant system boundary, i.e., the reactor coolant flows to the suppression pool in an uncontrolled manner.

The second situation is reportable under 10 CFR'50.72(b)(2)(ii), which requires the licensee to notify the NRC Operations Center for: .

Any event or condition that results in manual or automatic actuation of an Engineered Safety Feature (ESF), including theReactorProtectionSystem(RPS).

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Charles E. Norelius l An ADS valve is an ESF and its actuat' ion must be reported as soon as practical and in all cases within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the occurrence. An exception to this requirement is that actuations that are part of a preplanned sequence during testing or reactor operation need not be reported. So, testing of ADS valves need not be reported if it is in accordance with an approved procedure and if other reporting criteria in 10 CFR 50.72 are not triggered by something abnormal l in the testing. A test of an ADS valve that identifies multiple failures or a generic problem would be reportable even though the test was conducted as part of a preplanned sequence.

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drigli.! 5fona3In

f. C Md.n Edward L. -Jordan, Director Division of Emergency Preparedness and Engineering Response .

Office of Inspection and Enforcement ec: R. L. Spessard, RIII -

C. D. Anderson, RIII N. Chrissotimos, RIII ,

R. C. DeYoung, IE J. M. Taylor, IE Regional Administrators Distribution:

DCS RCDeYoung SASchwartz FHebdon EAB R/F JMTaylor CERossi JHeltemes DEPER R/F ELJordan EWWeiss RBaer 84478D

  • SEE PREVIOUS CONCURRENCES 11/ 84
  • DEPER:IE *DEPER:IE *DEPER:IE *DDDEPER:IE D:DEPER:IE -

EWWeiss:mj *DGable CERossi SASchwartz ELJordan 11/ /84 11/05/84 11/ /84 11/ /84 11/ '/84 4

9

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