ML17263A161
| ML17263A161 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/23/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-M51093, NUDOCS 9303050152 | |
| Download: ML17263A161 (8) | |
Text
ACCEIERAT DOCVMENT DIST VTION SYSTEM REGULATO INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9303050152 DOC.DATE: 93/02/23 NOTARIZED:
NO FACIL:50-234 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Provides info re mods to Engineering Work Requests
- 5161, 4970
& 5405,in ref to Insp Repts 50-244/89-80,50-244/91-01, Performance Insp 50-244/91-201,RG 1.97,emergency response capability a
NUREG 0737,Suppl l.
DZSTRZBUTZON CODE:
ROOZD COPZES RECEZVED:LTR.
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TITLE: OR Submittal: General Distribution DOCKET 05000244 D
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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69 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C. MECREDY Vice Prerident Gtnna Nuclear Production February 23, 1993 TELEPHONE AREACODE 7 $ 8 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Ginna Station Modifications Engineering Work Requests (EWR) 5161, 4970 and 5405 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter from R.C.
Mecredy (RG&E) to W.T. Russell (NRC),
"Inspection Report 50-244/89-80, Notice of Violation"7 dated April 12, 1990.
(b):
Letter from L.H.
Bettenhausen (NRC) to R.C.
Mecredy (RG&E),
"Inspection Report No.
50-244/91-01" dated January 26, 1991.
(c):
Letter from R.C.
Mecredy (RG&E) to A.R. Johnson (NRC),
"Regulatory Guide 1.97 Conformance, Emergency
Response
Capability, TAC No. 51093", dated July 13, 1990.
(d):
Letter from R.
C. Mecredy (RG&E) to A. R. Johnson (NRC),
Emergency
Response
Capability/NUREG 0737, Supplement 1,
dated October 14, 1992.
(e):
Letter from R.
C. Mecredy (RG&E) to S.
A. Varga (NRC),
"60-Day Response to NRC Service Water System Operational Performance Inspection (IR 50-244/91-201) " dated April 6, 1992.
Dear Mr. Johnson:
By letter dated April 12, 1990 (Reference a),
RG&E indicated that Engineering Work Request (EWR) 5161 had been initiated for a
modification to provide continuous direct indication and alarm of main steam line radiation at Ginna Station.
Currently, the radiation monitor chart recorders do not begin recording until alarm conditions are reached.
Continuous indication would improve the operator's ability to respond expeditiously prior to alarm conditions.
As noted in Inspection Report 91-01 (Reference b),
this modification was scheduled to be completed by May
- 1993, however, due to reprioritization of modification activities in the upcoming refueling outage, it has been rescheduled for completion tL 9S0S050152 ea0223 PDR ADOCK 05000244 8
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in May, 1994.
This delay in its implementation does not represent an immediate safety concern since the recorders do give indication once alarm conditions, which are below any safety limits, are reached.
Prior to that point, operators have continuous S/G Blowdown radiation monitoring as well as the steam line radiation indication on the plant process computer system (PPCS).
By letter dated July 13, 1990 (Reference c),
RGGE indicated that EWR 4970 had been initiated for a modification to install a
new flow instrument
- channel, redundant to existing Residual Heat Removal (RHR) flow channel FT-626.
The new flow channel would satisfy the post accident monitoring redundancy requirement for this variable, assigned as Type A, and would also provide input to the Reactor Vessel Level Monitoring System.
Attachment B to that letter stated that this modification was scheduled to be completed by May 1993.
This modification has been rescheduled until May, 1994 due to reprioritization of modification activities in the upcoming refueling outage.
The delay in its implementation is considered justified due to additional instrumentation that is available to the control room which can be used to determine excessive RHR flow, specifically, RHR pump motor ampere indication on the PPCS.
It should be noted that Regulatory Guide 1.97 Revision 3 does not generically require redundancy for this variable, (RHR flow/low pressure injection flow). It is RGSE's determination that this variable performs a Type A function (determination of excessive RHR pump flow during the sump recirculation phase post LOCA) that invokes the redundancy provision, which the modification is being designed to meet.
Reference (d) lists this variable's (f14) attributes.
By letter dated April 6, 1992 (Reference e),
RG&E indicated that inspection of underground Service Water System (SWS) piping (EWR 5405),
to address silting, biofouling,
- erosion, corrosion, and protective coating failure concerns, would take place during the 1993 refueling outage.
Due to the significant resources being expended as a result of replacing the Containment Recirculation Fan Coolers (CRFCs) during the 1993 outage, in lieu of the 1994-1997 time frame as originally planned, the underground piping inspection is being rescheduled for the 1994 refueling outage.
Flow tests have confirmed adequate flow, indicating that silting and bio-fouling are not concerns at present.
- Further, leakage caused by
- erosion, corrosion, or protective coating failure would be indicated by leakage monitored in the screenhouse basement.
Given the importance of replacing the CRFCs and the current indicators of adequate SWS underground piping integrity, this delay is considered justified.
Very truly yours, Robert C.
Me re SCK/255 Attachment
4 w II J) s
,Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 1
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
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