ML17309A259
| ML17309A259 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/27/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-04.C, TASK-3-4.C, TASK-RR NUDOCS 8205040387 | |
| Download: ML17309A259 (6) | |
Text
REGUL RY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NSR:8205000387 DOC ~ DATE! 82/04/27 NOTARI2ED!
NO
DOCKET FACIL:50"244 Robert Emmet Ginna Nuclear Planti Uni,t iE Rochester G
05000244 AUTH BYNAME AUTHOR AFF ILIATION MAIEREJ ~ E.
Rochester Gas K Electric Corp'ECIP
~ NAME,,
RECIPIENT AFFILIATION CRUTCHFIELDFD ~
Operating Reactors Branch 5
SUBJECT:
Forwards addi info per 811230 corn III"4.C to provide evaluation of missiles dur ing 1982 refueling ou in steam generator blowdown line DISTRIBUTION CODE!
A035S COPIES 'RECEIVED:
TITLE: SEP Topics NOTES:NRR/DL/SEP icy'itment re SEP Topic internally generated tape
~ Valve operator CV5738 should be restrained, LTR ENCL L SIZE:
05000244 RECIPIENT ID CODE/NAME ORB P5 BC 01 INTERNAL: NRR/DE/ADMQE 13 NRR/DL/ORAB 11 NRR/DS I /AEB G
04 COPIES LTTR ENCL 7
7 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME NRR/DE/HGEB 10 NRR/DL/SEPB 12 NRR/DSI/CSB 07 RGNl COPIES LTTR ENCL 2
2 3
3 1
1 1
1 EXTERNAL: ACRS 14 NRC PDR 02 10 1'0 1
1 LPDR NTIS 03 5
1 1
1 1
5P-TOTAL NUMBER OF COPIES REQUIRES:
LTTR PI ENCL Pf
I II I
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ZIZirrtiZ ZZ, ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAILER Vico Presldont 7cl.cnHD>C ARcA cDDK 7lo 546-2700 April 27, 19 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
SEP Topic III-4.C, Internally Generated Missiles R.
E. Ginna Nuclear Power Plant Docket. No. 50-244
Dear Mr. Crutchfield:
By letter dated February 17,
- 1982, the NRC provided a Safety Evaluation Report concerning the subject SEP topic, based on RGRE's assessment dated December 30, 1981.
In the December 30
- report, RGSE noted that additional evaluation of internally generated missiles would be performed by us during the Spring 1982 refueling outage, to address any remaining open issues.
The purpose of the attachment to this letter is to provide the promised information.
This information can be used to supplement the evaluation of this topic during the Integrated Assessment for Ginna.
RG6E has determined that the operator for valve CV5738 in the Steam Generator Blowdown line should be restrained.
All other concerns noted in RGGE's original assessment have been resolved based on inspection of valve location and orientation.
Very truly yours,
)D~~
(((
8205040387 820427 PDR ADGCK 05000244 P
. PDR
A J
C II k
4 K
Attachment:
Resolution of Open Issues for SEP Topic III-4.C, Internally Generated Missiles 1.
In Section V.2.b, Emer enc Core Coolin S stem (ECCS) of RG6E's December 30, 1981 assessment, it. was'stated that the ECCS would be capable of performing its safety-related
- function, even considering internally generated
- missiles, pending resolution of the location and orientation of valve 832B.
An in-containment inspection performed April 19, 1982 verified that the valve stem was not oriented toward any safety-related equipment.
- Thus, even a postulated failure of, the valve stem would not be of safety concern.
RG6E considers that this'ssue need not be further considered.
2.
In Section V.2.d, Chemical and Volume Control S stem (CVCS) it was noted that only valves HCV133 and RV203 needed to be evaluated for potentially damaging effects.
An in-containment inspection performed April 19, 1982 disclosed that these valves are located remotely from any safety-related cable
- trays, which is the only equipment considered to be of concern with respect to damage by potential CVCS letdown line missiles.
Thus, it can be concluded that the potential for damage due to internally-generated missiles from the CVCS is not of safety concern.
RG6E considers that, this issue need not be further considered.
3.
In Section V.2.p, Refuelin Water Stora e Tank, it was noted that internally-generated missiles could potentially affect the tank.
The April 19, 1982 inspection has disclosed that only valve stems associated with the Component Cooling Water and the Service Water Systems are oriented towards the RWST.
As stated in Sections V.2.f and V.2.g of RG6E's December 30, 1981 assessment, the fact that both of these syst.ems are low
- pressure, cold water systems would make it very unlikely that internally-generated missiles which could cause damage would occur.
Therefore, RG6E concludes that the effects of potential internally-generated missiles on the RWST is not of safety concern.
RG6E considers that this issue need not be further considered.
H 4.'n Section V".2.b, Steam Generator Blowdown, it was noted that
further,evaluation'of the potential for the valve genexator of valve CV5738 to become a missile would be made.
RG6E considers it. unlikely that this valve operator could become a
missile.
However, in order to provide further assurance that the potential failure would have no affect on safety-related components, RG6E plans to install a restraint on this operator.
The schedule for performing this modification will be determined during the Integrated Assessment.
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