ML20217K711
| ML20217K711 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/23/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217K707 | List: |
| References | |
| NUDOCS 9805040076 | |
| Download: ML20217K711 (3) | |
Text
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-4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION
~t WASHINGTON, D.C. 2055'A001 ok
,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I
RELATED TO AMENDMENT NO.126 TO FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By letter dated August 8,1997, as supplemented by letter dated November 10,1997, the Union Electric Company (UE) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-30) for the Callaway Plant, Unit 1 The proposed changes would revise the Technical Specifications (TS) to change feedwater isolation engineered safety features actuation system (ESFAS) functions in TS Tables 3.3-3,3.3-4, and 4.3-2.
The November 10,1997, supplemental letter provided additional clarifying information and did not change the staff's original no significant hazards determination that was published in the Federal Reaister on December 17,1997 (62 FR 66144).
2.0 TECHNICAL SPECIFICATION CHANGES AND EVALUATION 2.1 Actuation Logic Applicability The applicable modes for Functional Units 5.a.1), Automatic Actuation Logic and Actuation Relays (SSPS), and 5.a.2), Automatic Actuation Logic and Actuation Relays (MSFIS), in Tables 3.3-3 and 4.3-2 would be revised to add MODE 3. This change is proposed because the automatic actuation logic for closure of the main feedwater isolation valves (MFIVs) must be available in MODE 3 to establish a pressure boundary preventing diversion of auxiliary feedwater (AFW) flow, thereby ensuring delivery of AFW flow to at least two intact steam generators under accident conditions. As a result of this change in applicability, the end point of the action statements will be changed to hot shutdown. This change is more restrictive and is consistent with the applicability of other TS related to decay heat removal by the auxiliary feedwater (AFW) system. This change is acceptable.
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O 2.2 New Steam Generator Level Low-Low Functional Unit A new Functional Unit 5.d, Steam Generator (SG) Water Level Low-Low (for feedwater isolation only), would be added to Tables 3.3-3,3.3-4, and 4.3-2. This change is more restrictive. The main feedwater isolation valve (MFIV) isolation on SG water level low-low isolation was added to the plant design to address a concern that AFW flow could be fed back through the MFW system instead of to the SGs under certain break conditions. This isolation signal is credited in the analyses for the loss of non-emergency AC power, loss of normal feedwater, and feedwater system pipe break events. This isolation signal was not included in the original TS, which were based on the Westinghouse Standard Technical Specifications (STS), because neither the STS at the time nor the current STS include this isolation signal. While this isolation signal had not previously been included in the TS, the licensee stated that they have always performed surveillances on this isolation signal consistent with other automatic actuation logic and actuation relays applicable in MODES 1-3. This change is acceptable.
2.3 Trip Time Delay Applicability The applicable MODES in Table 3.3 3 for auxiliary feedwater (AFW) SG Water Level Low-Low Functional Units 6.d.1).c), Start Motor Driven Pumps Vessel Delta T (Power-1, Power-2), and 6.d.2).c), Start Turbine-Driven Pump Vessel Delta T (Power-1, Power-2), would be revised to delete MODE 3. Functional Unit 6.d.3)in Table 4.3-2 would also be revised to delete MODE 3.
This function is used to change the trip time delays depending on power level. At reactor thermal power less than or equal to 10 percent, the maximum trip time delay is enabled, and the maximum trip time delay should always be enabled in MODE 3. This change is acceptable.
2.4 Feedwater Isolation on P-4/ Low Tavg The Bases for Functional Unit 11.b, Reactor Trip P-4, in Table 3.3-3 would be revised to add a note allowing the feedwater isolation function on P-4 (reactor trip and bypass breakers open) coincident with low Tavg (Tavg s 564oF) to be blocked. The reason for the change is to decrease unnecessary cycling of the MFIVs and AFW system which adversely impacts startup and shutdown evolutions. This feedwater isolation function provides backup protection for excessive cooldown events and is not credited in any FSAR analyses. The licensee has propcsed to install a bypass switch to block this signal during startup and shutdown evolutions with Tavg s 564eF just prior to opening the reactor trip breakers. The feedwater isolation function would be restored by manually defeating the bypass prior to entering MODE 2. This change is acceptable.
2.5 Conclusion The staff has reviewed the licensee's proposed TS changes to reviso the feedwater isolation i
ESFAS functions. Based on the review, the st6 :oncludes that the proposed T3 changes are acceptable.
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3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Missouri 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 the 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 proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 66144). 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 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 isstWice of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: A. Cubbage Date: April 23, 1998 ED%'
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