NUREG-0800, Summary of 880908 Meeting W/Util in Rockville,Md Re Facility Auxiliary Feedwater Sys Operability.Handout Encl: Difference between revisions

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#REDIRECT [[NUREG-0800, Requests Description of QA Program Applied During Preparation of Advanced LWR Util Requirements Document & QA Program to Be Applied to Ensure That Future Changes Will Be Made in Controlled fashion.NUREG-0800 & Reg Guide 1.28 Encl]]
| number = ML20206H843
| issue date = 11/10/1988
| title = Summary of 880908 Meeting W/Util in Rockville,Md Re Facility Auxiliary Feedwater Sys Operability.Handout Encl
| author name = Kalman G
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name =
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000312
| license number =
| contact person =
| case reference number = RTR-NUREG-0800, RTR-NUREG-1286, RTR-NUREG-800
| document report number = NUDOCS 8811230378
| package number = ML20206H839
| document type = MEETING MINUTES & NOTES--CORRESPONDENCE, MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
| page count = 7
}}
 
=Text=
{{#Wiki_filter:..
ENCLOSURE 1 MEETING MINUTES NUCLEAR REGULATORY COMMISSION STAFF / SACRAMENTO MUNICIPAL UTILITY DISTRICT STAFF
 
==SUBJECT:==
RANCHO SECO AUXILIARY FEEDWATER SYSTEM OPERABILITY DATE:            SEPTEMBER 8, 1988 PLACE:          NRC HEADQUARTERS, WHITE FLINT NORTH, ROCXVILLE, MD PARTICIPANTS: Steve Crunk, SMUD            Dan Fadel, SMUD Eric Swanson, B&W          Jim Taylor, B&W Jim Miller, NRC            Calvin Moon, NRC John traig, NRC            Jerry Wermiel, NRC George Kalman, NRC Meeting Summary:    SMUD representatives described the Rancho Seco Auxiliary Feedwater ( AFW) System using handout (attached). SMUD basis for concluding that the AFW System was operable following failure of valve HV 20578 was presented. SMUD representatives also reiterated that although the AFW System is designed to minimize overcooling of the Reactor Coolant System, this feature is not part of the licensing bases and this function of the system is not required to meet single failure criterion. The SMUD rationale, as presented during the meeting is described in a letter to the NRC dated September 2,1988 (0.R. Keuter to G. Knighton).
l NRC staff agreed that alternate valve lineups as described in the September 2, 1988 letter appeared to correct innediate safety concerns. However, the staff did not agree with SMUD's design basis evaluation of the AFW System nor with the interpretation of the TS operability requirements for the AFW System.
SMUD representatives expressed the view that since redundant AFW train flow paths, which include valve HV 20578, were added during the 1986 outage, the redundant design is not part of the licensing bases and should not be included in TS operability requirements. The AFW train can perform its function with valve HV 20578 inoperable per the original plant design and licensing bases.
The NRC staff did not agree with this logic and pointed out that the pre-1986 Rancho Seco design did not meet the existing licensing requirements and this was the primary reason why the plant was shutdown for 27 munths. The resulting plant upgrades are described in the restart safety evaluation report, NUREG-1286.
Rancho Seco systems and design bases, as described in NUREG-1286, are part of the current license requirements.
The single failure proof requirements for the AFW system during a steam line rupture are described in NUREG-1286, Supplement 1 (page 3131). These requirements are based on the Standard Review Plan, NUREG-0800, Section 15.1.5.
Operations with valve HV 20578 failed closed would violate the single failure criterion.
SS11230378 seigio              s
<      PDR    ADOCK 05000312 P                  PDC
 
The staff also presented the following rationale for concluding that the AFW System was TS inoperable and that a 72 hour Limiting Condition of Operation (LCO) was in effect:
(1) Requirements for reactor criticality (72 hour LCO) as specified in TS Section 3.4.2.F include "Both auxiliary feedwater trains (i.e., pump and their flow path) are operable..."
(2) TS Section 1.3 defines operable. A system is operable when
                      "(2) it has been tested oeriodically in accordance with Specification 4 and has met its perfonnance requirements".
(3) TS Section 4.B.1 requires monthly testing of AFW pumps and Valves. During the monthly surveillance test on August 25, 1988, valve HV 20578 was found inoperable.
Per the TS sections cited above, the A7W train should have been declared inoperable.
The NRC staff voiced concern that there was inability at SMUD to interpret relatively basic licensing concepts and TS operability requirements. However, the staff also concurred with the views of the Babcock and Wilcox representa-tives thac the initiative displayed by SMUD in coming to NRC Headquarters to resolve this issue indicated a constructive attitude and a positive change from the pre-1986 SMUD management style, fk George Kalman, Project Manager w
Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
 
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s NRC PRESENTATION b              AUXILI ARY FEEDWATER SYSTEM /
                <              EMERGENCY FEEDWATER INITIATION h              AND CONTROL                            (EFIC) SYSTEM                                      i g              SEPTEMBER 8,1988                                                                        ,
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NUREG-0737, ITEM II.E.1.2                                                4 l
(1)            The design shall provide for the automatic init.lation of the AFWS.
(2)            The automatic initiation signals and circuits shall be designed so that a single a
failure will not result in the loss of AFWS function.
NUREG-0800, STANDARD REVIEW PLAN, SECTION 10.4.9 BRANCH TECHNICAL POSITION ASB 10-2, ITEM B.4 The auxiliary feedwater system should be designed with suitable redundance to offset the consequences of any single active component failure; however, each train need not contain redundant active components.
 
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SAFETY EVALUATION OF RANCHO SECO EMERGENCY FEEDWATER INITIATION AND CONTROL SYSTEM DESIGN i
DECEMBER 14, 1987 (page 36) 1 i      The staff has reviewed the operability requirements for EFIC system instrumentation, the required limiting conditions for operation (IIOs) and associated action statements for when operability requirements cannot be met, as listed in Table 3.5.1-1, "Instruments Operating Conditions," of the Rancho Seco Technical Specifications.
Table 3.5.1-1 has been modified subsequent to proposed Amendment No. 152, Revision 2, as agreed to by both the staff and the licensee. In general, if one of the four EPIC system channels monitoring a parameter becomes inoperable, it must be restored to service within seven days, or the reactor is to be placed in at least hot shutdown within the next 12 hours. Although seven days is longer than typically allowed by the Standard Technical Specifications (STS), the staff considers seven days to be acceptable because even with an inoperable channel, the EFIC system will perform its AFW initiation and MFW isolation functions given a single failure.
 
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,                    3.4.1.E                                            Both auxiliary feedwater trains (i.e., pumps and their flow paths) are operable.
3.4.2.F                                            Both auxiliary feedwater trains (i.e., pumps and their flow path) are operable except that:
(1)  With one auxiliary feedwater train inoperable, restore the train to operable status within 72 hours or be in hot shutdown within the next
;                                                                              6 hours and on decay heat cooling within the next 12 hours.
t l                                                                        (2)  With both auxiliary feedwater trains inoperable, the reactor shall be
!                                                                              made subcritical within four hours and the reactor shall be on decay
;                                                                              heat cooling within the next 12 hours.
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