ML20198B360
| ML20198B360 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/18/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198B351 | List: |
| References | |
| NUDOCS 9801060283 | |
| Download: ML20198B360 (4) | |
Text
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UNITE] STATES p:
j NUCLEAR REGULATORY COMMISSION
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S FETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.137 TO FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS. INC.
BIG FORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO,59-182 1.0 INTRODU(IlQH By, application dated July 17, 1996, as supplemented by letters dated June 3, a u July 7, 1997 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 existing TS 3.7.1.3, 00dDENSATE STORAGE POOL (CSP), by increasing the minimum required contained water volume in the CSP from 82 percent to 91 percent indicated level.
In tidition, by a July 7,1997, letter the licensee proposed to expand the applicability of TS 3.7.1.3 to include Mode 4 operational requirements. The proposed changes are required to ensure that the minimum useable water volume in the Condensate Storage Pool is maintained greater than or equal to 173,500 gallons. The new minimum level accounts for the minimum level required to prevent Emergency feedwater pump suction line vortexing, to account for instrument measurement uncertainties, and to satisfy the short term water requirements for the Component Cooling Water Makeup system.
Also, by application dated April 11, 1997, the licensee requested to delete l
Action (b) in TS 3.7.1.3 and its associated surveillance requirement.
The current technical specification allows the Wet Cooling Tower (WCT) basins to be used as the primary supply to the Emergency Feedwater (EFW) pumps extending EFW system operability up to 7 days in the event that the CSP were to become l
inoperable for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The proposed change will not allow this option.
2.0 EVALUATION 2.1 [gndgan,te Storace Pool Water Level The primary source of EFW is the CSP. The CSP is a steinless steel lined, l
reinforced concrete Seismic Category I pool located within the Reactor l
Au;:lliary Building (RAB). The CSP has a capacity of approximately 210,000 gallons and must be operable in modes 1, 2, and 3 with a contained volume specified in the current TSs.
The CSP, with the minimum water volume, 9901060283 971218 PDR ADOCK 05000382 P
, provides the primary source of water to the Reactor Coolant System (RCS) to shutdown coo'11ng entry conditions following any design basis accident. An additional source of water is stored in the WCT basins providing additional capability to maintain Hot Stanoby conditions for at least an additional two hours prior to initiating shutdown cooling.
The indicated level specified in the current TSs (82 percent) did not account for the artex phenomena or the instrumentation measurement uncertainties.
In addition, it did not account for the water required for the Component Cooling Water Makeup (CCWM) system. The proposed level of 91 percent (approximately 191,100 gallons) is based on having at least 173,500 gallons of useable water available to cool the RCS to shutdown cooling entry conditions following any design basis accident, thus ensuring that a minimum of 170.000 gallons of water will be available in the CSP to su) ply the Emergency feedwater system and 3500 gallons of w;ter will be availa)1e for CCWM to provide makeup for CCW, Essential Chilled Water, and Emergency Diesel Generator Jacket Hater systems following a tornado, LOCA, or seismic event, in addition, the proposed level allows 3.57 percent margin for vortexing with vortex breakers installed in CSP, and 4.96 percent margin for instrument measurement uncerta)nties.
By letter dated July 7,1997, the licensee requested that TS 3.7.1.3 be applicable in Mode 4 and the Limiting Condition for Operation be footnoted to indicate that a minimum CSP level of 11 percent be required in Mode 4.
The licensee Indicated that short term requirements for CCW Makeup have been l'ecluded in the design basis of the CSP to provide makeup for CCW, Essential Chilled Water, and Emergency Diesel Generator Jacket Water systems following a tornado, LOCA, or seismic event.
These systems are required to be operable in Mode 4.
In Mode 4. EfW is not required to be operable and therefore, the recuirement to maintain 170,000 gallons for EfW is not applicable.
Thus, in Moce 4, the licensee requested that only 11 )ercent be required to be available in the CSP to assure an adequate s1 ort term source for the CCW Makeup system. This level is based on having at least 3,500 gallons available for CCWM while accounting for the required level to suppress vortexing with vortex breakers installed and instrumentation measurement uncertainties.
If the CSP becomes inoperable while in Mode 4, the licensee has
)roposed an action to place the unit in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. T11s Action is modeled after the Cold Shutdown action statement contained in TS 3.0.3.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's model for pred1cting vortexing in EFW suction lines and determined that the licensee has provided a reasonable approach in estimating required vortexing margin after installing vortex breakers in the CSP. Considering additional l
margin provided for instrumentation measurement uncertainties, the staff l
concluded that the proposed increased minimum level will provide an adequate supply of water to the EFW and an additional 3,500 gallons of water will be available to provide makeup for CCW, Essential Chilled Water, and Emergency Diesel Generator Jacket Water systems following a tornado, LOCA, or seismic event. Also, additional changes to include Mode 4 in the TS for CSP are l
considered improvements in the current iSs. Therefore, the staff finds the l
l
0 3-l proposed changes a'cceptable. Also, corresponding changes in Bases Section 3/4.7.1.3 made by the licensee to reflect the new leve are appropriate and i
they are acceptable to the staff.
_2.2 Deletina of Action (b) in TS 3.7.1.3 j
modeledaccordingtoNUREG-0212, Revision 3,"CombustionEnineering(-
The current Waterford 3 TS 3.7.1.3 limiting condition for o eration LC0) was Standard Technical Specifications," which provides for an a ternate supply for emergency feedwater in the event the CSP is unavailable as the primary source.
The current TS (Action (b), TS 3.7.1.3) for Waterford 3 allows the WCT basins to be used as the primary supply to the EFW pumps extending EFW system operability up to 7 days in the event that the Condensate $torage Pool (CSP) were to become inoperable for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
I Recertly, the licensee and the NRC staff have identified some concerns for lining up the WCT basins as the primary source of EFW.
It was documented in NRC inspection report 96-12 as Notice of Violation (NOV) 9612-05.
Since the licenses could not provide an adequate basis for using WCT bash.s as the primary source of water for EFW when CSP is inoperable, the licensee has requested to delete Action (b) in TS 3.7.1.3 and its associated surveillance i
requirement in Surveillance Requirement 4.7.1.3.2.
The proposed change is conservative.
Therefore, it is acceptable to the staff.
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 to 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 sigaificant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a pro-posed finding that the amendment involves ne significant hazards consideration and there has been no public comment on such finding March 26, 1997 (62 FR Accordingly, the amenh(ent meets the eligiDility criteria (62 FR 19624).for categori 14461), July 30, 1997 62FR40849),andAntil 22, 1997 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.
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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 $ndangered 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 amendnent will not be inimical to the common defenre and security or to the health and safety of the public.
Principal Contributor:
C. Patel, NRR Date:
December 18, 1997 g
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