ML20134K932
| ML20134K932 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/12/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134K931 | List: |
| References | |
| NUDOCS 9702180023 | |
| Download: ML20134K932 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION if WASHINGTON, D.C. 2004H001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.122 TO FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS. INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By application dated June 27, 1996, Entergy Operations, Inc. (the licensee),
submitted a request for changes to the Waterford Steam Electric Station, Unit 3, Technical Specifications (TSs). The requested changes would modify TS 3/4.3.3.6, " Accident Monitoring Instrumentation," to reflect the Combustion Engineering improved Standard Technical Specification (STS) approved and issued as NUREG-1432.
This change revises the TS to include Accident Monitoring Instrumentation recommended in Regulatory Guide (RG) 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During an Following an Accident," Revision 3.
2.0 EVALUATION The proposed change modifies TS 3/4.3.3.6, " Accident Monitoring Instrumentation," by removing instrumentation from the TS which is not RG 1.97 Type A or Category I and by adding other instrumentation tt.t is not currently addressed by TS 3/4.3.3.6. The change also extends the allowed outage times for post accident monitoring instrumentation and replaces the HOT SHUTDOWN requirement with a Special Report requirement.
I The primary purpose of the accident monitoring instrumentation is to display plant variables that provide information required by the control room operators during accident situations. This information provides the necessary 1
support for the operator to take manual actions, for which no automatic control is provided, that are required for safety systems to accomplish their safety functions for Design Basis Events. The OPERABILITY of post accident monitoring (PAM) instrumentation ensures that there is sufficient information i
available on selected plant parameters to monitor and assess plant status and behavior following an accident.
The availability of post accident monitoring (PAM) instrumentation is important so that responses to corrective actions can be observed and the need for, and magnitude of, further actions can be determined.
These essential instruments have been identified by Waterford 3 per the recommendations of Regulatory Guide 1.97, as required by Supplement I to NUREG-0737, "TMI Acti:n 9702180023 970212 PDR ADOCK 05000382 P
Items". By letter dated February 28, 1991, Waterford 3 changed its commitment from RG 1.97, Revision 2 to Revision 3 and submitted information regarding the implementation of RG 1.97, Revision 3.
The NRC staff's safety evaluation dated July 12, 1993, accepted the Waterford 3 submittal as being in conformance with, or justified in deviating from, the guidance of RG 1.97, Revision 3.
As discussed in NUREG-1432, only Type A and Category 1, non-Type A, instrumentation are expected to be included in the TSs for accident monitoring instrumentation.
In addition to Type A and Category 1 instruments, the current Waterfcrd 3 TS 3/4.3.3.6 includes the following RG 1.97 Category 2 instruments:
Steam Generator Pressure, Refueling Water Storage Pool Water Level, Emergency Feedwater Flow Rate, Reactor Coolant System Saturation Margin Monitor, Safety Valve Position Indicator, and Containment Water Level (Narrow Range). The proposed change will remove these Category 2 instruments from the requirements of TS 3/4.3.3.6.
This change is consistent with the CE improved STS and associated safety analyses which require only RG 1.97 Type A and Category 1, non-Type A instrumentation, and the staff considers this acceptable.
The proposed change also adds Containment Pressure (Wide-Wide Range) i instrumentation to TS 3/4.3.3.6 to distinguish this instrumentation from the Containment Pressure (Wide Range) instrumentation. The current Waterford 3 TS 3/4.3.3.6 requires 2 channels for Containment Pressure, but does not specify between Wide Range and Wide-Wide Range instrumentation.
Both variables are required by RG 1.97, and both are designated as Category 1.
The staff finds this change acceptable.
The proposed change further revises the number of required channels of Steam Generator Water Level (Wide Range) from 1/ steam generator to 2/ steam generator. This is consistent with NUREG-1432, and the staff considers this acceptable.
Other Type A and/or Category 1 instrumentation that is not included in TS 3/4.3.3.6 is included in other TS. This instrumentation is Containment Area High Range Radiation (TS 3/4.3.3.1), Containment Hydrogen Concentration (TS 3/4.6.4.1), and Radioactivity Concentration (Gamma Spectrum) (TS 6.8.4.d).
The requirements for this instrumentation remain unchanged, and the staff I
finds them acceptable.
Log Power Indication (Neutron Flux) is currently included in TS 3/4.3.1,
" Reactor Protective Instrumentation." Channels C and D are credited for meeting the requirements of RG 1.97. The proposed change will add these channels to TS 3/4.3.3.6 to ensure that LC0 and other related Actions for these channels are consistent with the other accident monitoring instrumentation.
l The proposed changes also revise the Action requirements and associated Allowed Outage Times (A0T) for TS 3/4.3.3.6 to be consistent with those j
outlined in NUREG-1432. The A0T for cne INOPERABLE channel will be changed from 7 days to 30 days.
If the required channel is not restored to operable status within 30 days, it requires to prepare and submit a special report to j
l
. the Commission within 14 days outlining the actions taken (including the preplanned alternate method of monitoring), the cause of the inoperability, and the plans and schedule for restoring the inoperable channel to operable status. Tie 30 day Completion Time and reporting requirements are consistent with NUREG-1432 and is, therefore, acceptable to the staff.
l The A0T for two INOPERABLE channels will be changed from 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to 7 days.
The 7 day Completion Time is consistent with NUREG-1432 and is, therefore, acceptable to the staff.
Finally, the proposed changes in BASES section of TS 3/4.3.3.6 are consistent with the discussion provided in NUREG-1432 and is, therefore, acceptable to the staff.
Based on the above, the staff concludes that the proposed changes to the Waterford, Unit 3 TS are consistent with NUREG-1432 and are, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a pro-posed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (61 FR 40017).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in I
connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
1 Principal Contributor:
F. Gee, NRR/HICB Date:
February 12, 1997 4
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