ML17262A574
| ML17262A574 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/05/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 9108120255 | |
| Download: ML17262A574 (4) | |
Text
ACCELERATED DISTRIBUTION DEMONSTPATION SYSTEM I
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CESSION NBR:9108120255 DOC.DATE: 91/08/05:
NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant,'nit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION MARTIN,T.T.
Region 1 (Post 820201)
SUBJECT:
Responds to NRC ltr re violations noted in insp rept 50-244/91-11 on 910606.Corrective actions:investigating multi-channel communication sys-
& unresolved item 50-244/89-81-03 has been completed upon approval analysis.
DISTRIBUTION CODE:
IEOID COPIES RECEIVED:LTR ENCL 0
SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response R
D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
r 05000244 A
RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: AEOD AEOD/TPAB NRR MORISSEAU,D NRR/DLPQ/LPEB10 NRR/DREP/PEPB9H NRR/OTSB 11E22 NUDOCS-ABSTRACT OGC/HDS1 RGN1 FILE 01 EXTERNAL: EG&G/BRYCE,J. H.
NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME JOHNSON,A AEOD/DEIIB DEDRO NRR SHANKMAN,S NRR/DOEA/OEAB NRR/DST/DIR 8E2 NRR/PMAS/ILRB12 OE DI~
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0 NRC PDR COPIES LTTR ENCL D
D R
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NOTE TO ALL"RIDS" RECIPIENTS PLEASE HELP US TO REDUCE I'i'ASTE! CONTACT THE DOCUMENT CONTROL DESK, ROON I P 1-37 (EYT. 20079) TO ELIliIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUliIENTS YOU DON'T NEED!
ZOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL A
, D D
ROCHESTER GAS AND ELECTRIC CORPORATION
~
I yf 6'"ngv 89 EAST AVENUE ROCHESTER N K.14649 0.001 ROBERT C. MECREDY Vice Pretident Cinn8 Nucle81 Production August 5, 1991 TEt.EPHONE AREACODE 716 546 2700 Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA,19406
Subject:
Response
to Inspection Report 50-244/91-11 dated June 6,
1991 R.E.
Ginna Nuclear Power Plant Docket Number 50-244
References:
(a) Letter from Robert M. Gallo, NRC Region 1, to Robert C.
- Mecredy,
Subject:
Inspection Report 50-244/90-80, dated July 17, 1990 (Section 7.1)
(b) Letter from Robert C. Mecredy, RG&E to Thomas T.
Martin, NRC Region 1,
Subject:
Response
to Main-tenance ActivityWeaknesses Identified in Inspec-tion Report 50-244/90-80, dated September 19, 1990 (weakness Number 2)
(c) Letter from, Marvin W. Hodges, NRC, to Robert C.
- Mecredy, RGE,
Subject:
NRC Safety System Func-tional Inspection Team Report No.
50-244/89-81, dated May 9, 1990 (Section 2.2.1.5).
(d) Letter from Robert C. Mecredy, RG&E to Thomas T.
- Martin, NRC Region 1,
Subject:
SSFI-RHR System, dated June 8,
1990 (Encl. E).
Dear Mr. Martin,
The subject inspection report did not require a written
.response, however, 'the status and actions requested on two of the items within the inspection report differ from previous commitments made by RG&E.
Section 3.1.2-Weakness No.
2 Potential Exists for Miscom-munications due to Sound Powered Phone Limitations Reference (a) identified a
weakness that miscommunication caused by the existing sound-powered phone system could trigger possible problems
- and, therefore, constitutes a potential safety concern.
RG&E acknowledged in reference (b) that the single channel sound-powered phone system presents communication limita-8 1 ~l(/~PC t
~i 1 OQC F-'6.>Pc
?,1 -,
~D - Cg O~OOO>4 re
tions during the period of heavy use associated with maintenance and testing activities encountered during the refueling outage.
RG&E indicated that a multi channel communication system is being investigated.
Section 3.1.2 of the subject inspection report indicated that the multi-channel system would be operational by June
- 1991, based upon an estimated completion date provided by Ginna Station personnel duiing the April 22-26, 1991 inspection.
While it is RG&E's intent to improve upon the limitations of the existing single channel system, a multi-channel system is currently not operational and the plans. for, these improvements are still being evaluated.
Because we considered this discussion with the inspector to be a status update only and subject to change, the finalizing of these plans and the subsequent implementation of such a
system remains to be integrated into the overall schedule of work.
No firm date for completion of this project is presently available.-
Section 3.2.2 (0 en) Unresolved Item 50-244/89-81-03 Reference (c) initiated unresolved item 50-244/89-81-03 and indicated that the item was considered unresolved pending comple-tion'f the licensee evaluation and determination of the adequacy of the vendors calculations.
This was based on the inspection finding that the consultant's independent analysis may have been too conservative in the modeling of the Net Positive Suction Head (NPSH) problem.
Based on approval of RG&E analysis NSL-0000-DA027 "Residual Heat Removal (RHR) Pump NPSH Calculations During Accident Conditions" dated 5/20/91, and implementation of changes to Emergency Procedure ES 1.3, it is considered that all actions required for this unresolved item have been completed by RG&E.
Very truly yours, Robert C. Mecre GAH/178 xc:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 Ginna Senior Resident Inspector