ML17254A931
| ML17254A931 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/30/1984 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Paulson W Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0944, RTR-NUREG-944 NUDOCS 8409060213 | |
| Download: ML17254A931 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR:8409060213 DOC ~ DATE:'80/08/30 NOTARIZED:
NO DOCKET ¹ FACIL:50 240 Robert Emmet Ginna Nuclear Planti Unit ir 'Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION KOBER~R ~ 'l0, Rochester Gas 8 Electr ic Corp.
RECIP ~ NAME~
RECIPIENT AFFILIATION PAULSON~H ~ AD Operating Reactors Branch 5
SUBJECT:
Updates several commitments described in SER (NUREG 0940) re full>>termOL;High energy sources removed from cantrol bldg, Seismic piping upgrade program mods will be completed during 1985 8
1986 refueling outages, DISTRIBUTION 'CODE:
A001D
.COPIES RECEIVED:LTR ENCL SIZE' TITLE; OR Submittal:
General Distribution NOTES;NRR/DL/SEP
- 1cy, OL: 09/19/69 05000244 RECIPIENT ID CODE/NAME'RR ORBS BC 01 INTERNAL; ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB'RR/DS I/RAB RGN1 COPIES LTTR ENCL 1
1.
1 1'
RECIPIENT ID CODE/NAME ELD/HOSE NRR/DL DIR NR /DS I/METB 04 COPIES LTTR ENCL EXTERNALS ACRS NRC PDR NTIS NOTES:
09 02 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 27 ENCL
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R BRF 0/f///II IIZEI8 ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER VICe PIIESIDENT ELECTRIC 6a STEAM PRODUCTION TELEPHONE AREA coDE Tld 546-2700 August 30, 1984 Director of Nuclear Reactor Regulation Attention:
Nr. Walter A. Paulsoni Acting Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
FTOL Supplement R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Paulson:
The purpose of this letter is to update several commitments described in NUREG-0944I the R.
E. Ginna "Safety Evaluation Report Related to the Full-Term Operating Licensei" October 1983.
Section 3.5 RGGE committed to eliminate high energy steam lines from the relay room and air handling room.
This commitment was met during the 1984 refueling outage by removing the sources of high energy from the control building.
The steam supply and relief lines and condensate return lines have been cut and capped or welded outside the control building.
2.
Section 3.6(2)
RGGE stated that the seismic piping upgrade program was expected to be completed by the end of the 1984 refueling outage.
The majority of this effort has been accomplished.
However>
some additional analysis and installation must still be performed.
RGSE expects to complete any additional modificationsi if necessary>
during the 1985 and 1986 refueling outages.
3.
Section 3.6(3)
RG6E committed to provide additional seismic support for the four essential service water pumps and the component cooling water surge tank.
Both of these modifications were completed prior to the end of the 1984 refueling outage.
4 Section 3.6(3)(b)
RG6E committed to provide additional seismic support for the sodium hydroxide tank.
This modification was completed prior to the end of the 1984 refueling outage.
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ROCHESTER GAS AND ELECTRIC CORP.
DATE August 30 i 1984 Mr. Walter A. Paulson SHEET NO.
5.
Section 3.6(4)
RGGE committed to complete the analysis and submit the report concerning the seismic capability of the main control board.
This report> entitled "Seismic Structural Evaluation of the Main Control Board>"
was submitted with RGSE's letter of January 9<
1984 relative to SEP Topic III-6> "Seismic Design Considerations".
Based on the recommendations contained in that report<
RGGE determined that modifications to enhance the structural integrity of the main control board should be performed.
These modifications were completed during the 1984 refueling outage.
Section 6.2 RGGE proposed to implement a number of modifications>
both procedural and hardware> relative to the containment fluid system penetrations.
The procedural modifications<
which consisted of locking certain valves in position and performing Appendix J Type "C" leak testing on them, were completed during the 1984 refueling outage.
The hardware modifications>
which include the addition of another valve in the seal return line and the enhancement of the fan cooler service water isolation valves<
are scheduled to be completed during the 1986 refueling outage.
7.
Section 9.2 RGGE proposed to add a redundant component cooling water surge tank level indication in the control room.
This modification was completed prior to the end of the 1984 refueling outage.
r truly yours>
R r W. Kober
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