ML20057F867
| ML20057F867 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/15/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F863 | List: |
| References | |
| NUDOCS 9310190263 | |
| Download: ML20057F867 (3) | |
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NUCLEAR REGULATORY COMMISSION
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIQN j
RELATED TO AMENDMENT NO. 51 TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL, PERRY NUCLEAR POWER PLANT. UNIT NO. I DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated March 16, 1992, Centerior Energy (the licensee) requested a change to the Perry Nuclear Power Plant, Unit 1, Technical Specifications (TSs).
Specifically, the licensee proposed to revise Table 3.3.7.4-1, " Remote l
Shutdown System Controls." The proposed change would remove the line item (in Table 3.3.7.4-1) for the controls to the Reactor ; ore Isolation Cooling (RCIC) pump discharge to lube oil cooler valve.
2.0 EVALUATION The proposed change has been requested in order to implement a design change which would convert RCIC valve IE51-F046 from a normally closed (NC) motor operated valve (MOV) to a locked open (LO) manually operated valve. The MOV will be disabled electrically from the motor control center, Control Room and Remote Shutdown Panel. The valve will be locked in the normally open position and may be closed for maintenance purposes by the actuator handwheel only.
The current design requires the valve to open automatically from its NC l
position on a RCIC system initiation signal to supply cooling water to the RCIC lube oil cooler. This design is a carry-over from a previous BWR design where the cooling water from the RCIC pump discharge was routed through the lube oil cooler and then to the RCIC barometric condenser. The cooling water l
was sprayed into the barometric condenser and wn then routed to the Main I
Condenser through the barometric condenser drain.
In the previous BWR design, I
this valve needed to be closed after RCIC system operation to prevent draining water from the Condensate Storage Tank to the Main Condenser. New BWR designs, such as those utilized at Perry do not utilize a Barometric Condenser. The lube oil cooler outlet is returned to the RCIC pump suction line, making this a closed loop operation.
In this design, there is no concern of a water drainage problem to the Main Condenser, thus there is no need for this valve to close after RCIC system operation. Therefore, valve IE51-F046 can be changed to a manually operated open valve without adversely affecting system performance. This design change was approved by General Electric, the Nuclear Steam Supply System (NSSS) supplier for Perry.
9310190263 931015 PDR ADDCK 05000440 P
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- If the TS amendment is approved, the valve will be locked in the normally open position and cooling water to the RCIC lube oil cooler will always be available whenever RCIC pump IE51-C0001 runs. By converting the valve from a NC MOV to a LO manual valve, the valve will always be open to allow cooling water to the lube oil cooler. There is no need for the valve to close when the RCIC system is not running because this is a closed loop design.
By leaving the valve in the ncrmally open position the operability of the RCIC system is enhanced as it removes one active component from the system and replaces it with a passive valve. RCIC system operation from the Control Room and from the Remote Shutdown Panel as required by General Design Criteria 19 (USAR section 3.1.2.2.10) will not be affected because this will be a L0 manual valve which requires no remote operation.
Implementation of this design change will redu:e periodic preventive maintenance costs, and will eliminate costly diagnostic testing and Equipment Qualification inspection work.
Elimination of this Direct Current (DC) MOV will also reduce the load on the station battery.
Based on the above evaluation, the staff concludes that removal of the line item for the controls to the RCIC pump discharge to lube oil cooler valve from PNPP Unit 1 TS 3/4.3.7.4, Table 3.3.7.4-1, " Remote Shutdown System Controls" is acceptable.
The basis for the staff acceptance of the proposed modification are:
(1) This change will improve system reliability and thereby enhance plant safety by removing one active component from the RCIC system by replacing it with a passive valve, and (2) this design change will also reduce station battery loads.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0
[NVIRONMENTAL CONSIDERATION This amendment involves a change to a requirement with respect to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change to a surveillance requirement. The 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 28206). Accordingly, this 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 er environmental assessment need be prepared in connection with the issuance of this amendment.
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5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above,-that:-
.(1) there is rea;onable 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 regulatiots,-
and (3) the issuance of this amendment will not be inimical to the common y
defense and security or to the health and safety of the public.
Principal Contributor:
M. Razzaque l
I Date:
October 15, 1993 i'
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