ML17262A813
| ML17262A813 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/03/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9204150163 | |
| Download: ML17262A813 (4) | |
Text
ACCELERATED DISTRIBUTION DEMONSTPATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) gW ACCESSION NBR:9204150163 DOC.DATE: 92/04/03 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 R
SUBJECT:
Advises that that util identified inconsistency in containment. isolation boundary listed in TS Table 3.6-1 for containment penetration 103,const fire svc water.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR Q ENCL S
SIZE: M TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)
D 05000244 A
RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTS B11 NRR/DST/SELB 7E NRR/DST/SRXB 8E 0 -/Z 01 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC COPIES LTTR ENCL D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL
/
//////////////
/////////////
'I/ajar
/Zero
///////8+K~
////////////
ROCHESTER GAS AND ELECTRIC CORPORATION
/
roert o
89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY Vlcc Prerldent Clnna Nuclear Production April 3, 1992 TELEPHONE AREACODE 7 le 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Rochester Gas and Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
On March 31, 1992, RGGE identified an inconsistency with respect to a containment isolation boundary listed in Technical Specification Table 3.6-1 for containment penetration
- 8103, Construction Fire Service Water (NCR 892-101).
This table identifies a welded flange as one boundary for this penetration and a locked closed valve as the other boundary.
- However, after performing a
walkdown in support of upgrading station testing procedures with respect to containment penetrations, it was discovered that a bolted pipe flange exists inside containment and a locked closed valve and pipe cap outside containment.
A review of background information related to this containment penetration determined that the boundaries identified in Technical Specifications for this penetration have not been revised since Table 3.6-1 was originally added in 1980.
No record of a
change to the pipe inside containment could be found in plant records;
- thus, the 1980 submittal was in error.
A review was also performed with respect to the Systematic Evaluation Program (SEP) of Ginna.
The Final Safety Evaluation Report associated with SEP Topic VI-4 (see letter from D.
Crutchfield, NRC, to J. Maier, RGGE, dated April 12, 1982.) states that "Line 103, the construction fire service water line, is no longer in use, has a pipe cap inside containment, a locked-closed valve outside containment, and a welded cap outside...
Thereforeg GDC 56 is met on some other defined basis..."
It appears that the NRC reached the conclusion about a welded cap on the basis of the Technical Specification table since earlier correspondence from RG6E does not describe a welded cap for this penetration.
- Instead, RGEE stated that "a pipe cap inside containment and a locked closed valve outside containment form the penetration boundaries" (see letter from J. Maier, RGGE, to D. Crutchfield, NRC, dated December 30, 1981).
DOCS pgppp244 'I
)q) 4)QP$ +Q 92P4PS lTri PDR pDR F'
=>.PW Sa" rw>
=
v
~ s It
,('" 'An examination of the containment penetration testing program at Ginna identified that the pipe flange inside containment and the locked closed valve outside containment are currently being tested in accordance with 10 CFR 50 Appendix J.
In addition, these two barriers have consistently passed all leakage tests.
Therefore, it is the opinion of RGEE that the listing of a welded flange for penetration 4103 is a non-critical informational error since two barriers already exist for the penetration consistent with system design.
- However, RGGE has determined that, it is prudent to weld close the pipe inside containment since the penetration communicates with containment atmosphere.
This activity is expected to be completed during the current 1992 refueling outage.
In addition, RGGE has reviewed the other penetrations listed in Technical Specification Table 3.6-1 and. determined that all identified components are currently installed and tested as required except for manual va'lve 4647 for containment penetration
- f320, Service Water To "C"
Fan Cooler.
The correct isolation boundary for this penetration is manual valve 4641 since 4647 is a drain valve on the return line from the- "C" Fan Cooler.
This is considered to be a typographical error since the Final Safety Evaluation. Report for SEP Topic VI-4 shows that the NRC evaluated penetration 4320 assuming that 4641 was the containment boundary.
RG6E is also performing a review of the containment isolation boundaries for Ginna in response to the NRC request for additional information concerning the Amendment Request to remove the listing of containment isolation valves from Technical Specifications (see letter from A. Johnson, NRC, to R. Mecredy, RGGE, dated September 26, 1991).
This effort is scheduled to be completed shortly after the current refueling outage.
Ver truly yours, Robert Mecr dy MDFN387 XC Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington~
D.C. 20555 Ms. Donna Ross New York State Energy Office U.S. Nuclear Regulatory Commission Region 1
475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector