ML20202H962

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SER Accepting Change to EALs Used in Classification of Emergency Conditions
ML20202H962
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 02/03/1999
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20202H959 List:
References
NUDOCS 9902090014
Download: ML20202H962 (2)


Text

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L L* tog p k UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2000H001

%, . .. . . /g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON REVISED EMERGENCY ACTION LEVEL STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499

1.0 INTRODUCTION

By letter dated April 22,1998, STP Nuclear Operating Company (STPNOC, the licensee) submitted a proposed change to the South Texas Project, Units 1 and 2 (STP), emergency action levels (EALs) used in classification of emergency conditions. This EAL change is part of the corrective actions made in response to the identification of an error in the steam generator just-in-narrow-range emergency operating procedure setpoint.

2.0 BACKGROUND

The proposed revision to the STP EALs was reviewed against the requirements of 10 CFR 50.47(b)(4) and Appendix E to 10 CFR Part 50.

10 CFR 50.47(b)(4) specifies that onsite emergency plans must meet the following standard: "A standard classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee..."

i Appendix E, Subsection IV.B specifies in part that "...These emergency action levels shall be discussed and agreed on by the applicant and State and local govemmental authorities..."

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Appendix E, Subsection IV.C specifies that "... Emergency action levels (based not only on onsite and offsite radiation monitoring information but also on readings from a number of sensors that indicate a potential emergency, such as pressure in containment and response of the Emergency Core Cooling System) for notification of offsite agencies shall be described... The emergency classes defined shall include (1) notification of unusual events, (2) alert, (3) site area emergency, and (4) general emergency."

3.0 EVALUATION l

The licensee changed the steam generator narrow range level setpoint in EAL-1 and EAL-2 )

under initiating condition SS4, " Complete Loss of any Function Needed to Achieve or Maintain l Hot Ghutdown," from 5 percent to 14 parcent (this change is for non-adverse containment I conditions; a corresponding change was made to the setpoint for adverse containment I conditions, i.e.,26 percent to 34 percent). The original setpoint was intended to correspond to water level at the top of the tube bundle which also corresponded to the emergency operating procedure (EOP)"Just-in-narrow-range" setpoint. As reported in Licensee Event Report 98-002, an error was made in the identification of the location of the lower narrow range levelindication

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9902090014 990203 ENCLOSURE PDR ADOCK 05000498 F PDR .

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I tap relative to the tube bundle such that the top of the tube bundle was actually at the 14 percent j narrow range indication rather than at the 5 percent indication. As part of its corrective actions, i

the licensee changed the "just-in-narrow-range" EOP setpoint to 14 percent. This change in the EAL setpoint is being made to correspond to the EOP change. The basis for the EAL is not

{ affected by this change.

i The licensee stated in the April 22,1998, letter that the proposed changes had been presented to State and local authorities and that they have provided their approval.

4.0 CONCLUSION

The proposed change to the steam generator level setpoint for the EALs under initiating

condition SS4 does not change the basis for the original EALs. Therefore, these EALs continue
to meet the standards in 10 CFR 50.47(b)(4) and the requirements in Appendix E to 10 CFR i
Part 50.

Principal Contributors: E. Fox l J. O' Brien i

Date: February 3, 1999 l

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