ML20238E068
| ML20238E068 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/02/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20238E067 | List: |
| References | |
| NUDOCS 8709140110 | |
| Download: ML20238E068 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
SUPPORTING AMENDMENT NO. 103 TO FACILITY OPERATING LICENSE NO. NPF-3 TOLEDO EDISON COMPANY AND 4
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. I DOCKET NO. 50-346
- 1. 0 INTRODUCTION By letter dated February 18, 1987, Toledo Edison Company (TED or the licensee) requested amendment to the Technical Specifications (TSs) appended to facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1.
The proposed amendment would add new Limiting Conditions for Operation (LOCs) and Surveillance Requirements (SRs) for the Motor Driven Feedwater Pump (MDFP) System.
2.0 BACKGROUND
In NUREG-1177, " Safety Evaluation Report related to the restart of Davis-Besse Nuclear Power Station, Unit 1, following the event of June 9, 1985," dated June 1986, the NRC staff evaluated the newly proposed MDFP system and required the licensee to submit a proposed TS for the system for staff review within 60 days af ter restart.
The Davis-Besse restart occurred December 22, 1986, and by letter dated February 16, 1987, the licensee submitted proposed Technical Specification 3/4.7.1.7 for the MDFP system.
3.0 EVALUATION The MDFP system consists of one MDFP that can be powered from either emergency diesel generator and can be lined up to feed the steam generators via the main feedwater (MFW) system or the auxiliary feedwater (AFW) system (greater than 40% reactor power); flow to either steam generator can be controlled from the control room via the MFW control valves. When lined up to the AFW system, the total flow from the pump can be throttled by use of a control valve at the discharge of the pump, but flow control to individual steam generators is accomplished locally via manual valves.
Therefore, if flow balancing or isolation of flow to either steam generator is necessary, it must be done locally.
The MDFP is manually initiated at all times when it is lined up to either the AFW system of MFW system.
For a further description and evaluation of the 8709140110 870902 PDR ADOCK 05000346 P
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^ MDFP system, refer to NUREG-1177, where the staff concluded that the system design is acceptable.
It should be noted that because of the manual initiation feature in lieu of automatic interaction, the potential adverse effect related to overcooling or overfeeding the steam generators because of the additional cuoling capability resulting from
.the MDFP is greatly reduced.
The proposed TS for the MDFP system is similar to the existing TS for the AFW system in that it provides operability requirements during Modes 1, 2 and 3, and if.found to be inoperable, provides an LCO of restoring operability within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or placing the plant in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed TS also provides SRs for the MDFP system and provides the basis for including the MDFP system in the TSs.
The proposed TS ensures that pump and valve operability are verified and demonstrated on a periodic basis.
Specifically, every 31 days, the MDFP will be started from the control room and indication of flow will be verified.
When in Mode I with power greater than 40%, each MDFP system valve will be. verified to be in its correct position for line up to feed the steam generators via the AFW system.
When in Mode 1 with power equal to or less than 40% power, verification that each valve in the MDFP flow path is able to be positioned locally for delivering flow to the AFW system is performed every 31 days.
This verification is performed by noting the presence of handwheels for all manual valves or an available power supply or handwheels for the motor operated valves.
At least once per 92 days and prior to entry into Mode 3 from Mode 4, proper operation of the MDFP and each power operated and automatic valve in the MDFP flow path to the AFW system is verified.
This is more comprehensive than the 31-day HDFP test which only demonstrates the pump's capability to rotate and pump fluid.
At least once every 18 months, verification that a flow path exists between the MDFP system and the AFW system is accomplished by pumping water from the condensate storage tanks (CSTs) to the steam generators.
The flow path to the steam generators is verified prior to entering Mode 3 from Mode 4 by either stesm generator level change or AFW flow indication.
Verification of the operability of the MDFP lube oil interlocks and proper operation of all manual valves is also performed at least once every 18 months.
In addition, flow path verification is performed following each extended cold shutdown greater than 30 days in duration and following any modification or repair to the MDFP system that could affect the system's capability to deliver water from the CSTs to the AFW system.
The proposed Bases Section of the TSs (B 3/4.7.1.7) provides the basis for inclusion of the MDFP system in the TSs and describes the purpose of the operability requirements.
Further, the proposed TS satisfies the requirements of General Design Criterion 46, " Testing of Cooling Water Systems" for ensuring operability of the active components and the operability of the system as a whole.
Therefore, the proposed TS e
- 1 adequately responds to the staff's. requirement for TSs identified in NUREG-1177.
The LCO and SRs are similar to the existing TSs for the AFW i
system and are consistent with the intent of'the Babcock & Wilcox Standard l
Technical Specif3c.stions (B&W-STS) for the AFW system.
The primary 1
differences between the MDFP system and the-AFW system specifications arise from the f6ct that the MDFP system is manually-initiated and controlled, while the AFW system is automatically initiated and controlled.
Based on our review,.we conclude that the proposed TS for the MDFP system, including the Bases Section, satisfies the requirements of GDC 46, addresses the NRC staff's concerns identified in NUREG-1177 for improved AFW system reliability by ensuring MDFP operability, and is consistent with the B&W-STS for the AFW system. We therefore conclude that the proposed TS is acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to 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 a change to the surveillance requirements. We have tietermined 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 signifi-cant 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.
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 nor environmental assessment need be. prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
We'have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this smendment will not be inimical to the common defense and the security nor to the health and safety of the public.
Prinicipal Contributors:
W. LeFave J. Wermiel Dated: September 2, 1987
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