ML18143A964
| ML18143A964 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/29/1976 |
| From: | Koprowski R Rochester Gas & Electric Corp |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18143A964 (4) | |
Text
U.S. NUCLI AR REGULATORY C ISSION NRC FoRM 195 (2.76) a NRC DIBTRI~BU>tON sos PART BO DOCKET MATERIAL DOCKET NUMBER FILE NUMBER TO:
Mr Pubjhle Rochester Gas
& Elec Corp Roches,ter, NY RP Koprowski DATE OF DOCUMENT 4-29-76 DATE RECEIVED SLETTER.
IBORIGINAL ClcoP Y DESCRIPTION ONOTORIZED l9 UN C LASS I F I E D PROP INPUT FORM ENCLOSV RE NUMBER OF COPIES RECEIVED one sipned Ltr furnishing addi info conderning main steam isolation valves
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>O NOT SEMOR PLANT NAME RE Girma SAFETY FOR ACTION/INFORMATION ENVIRO 5-10-76
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ehf ASSIGNED AD:
BRANCH CHIEF:
PROJECT MANAGER; LXC~
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BRANCH CHXEF
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PROJECT MANAGER:
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NRC PDR X&E D
GOSSICK & STAFF CA ANA PROJECT MANAGEMENT BOYD P,
COLLINS HOUSTON PETERSON MELTZ HELTE1'IHS SKOVHOLT LPDR c
HNC NHE N
KNXGHT SIHIKXL PAMLXCKX REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBHRG EXTERNAL DISTRIBUTION NATL LAB REG V"XE ISTRI BUTION BENAROYA IPPOLXTO OPERATXNG REACTORS STELLO OPERATING TECH EISENHUT SHAO SCHMENCER GRIMES SITE SAFETY & HNV R ANALYSIS DENTON & MULLER 13ROOK11AVEN NATL LAB ULRIKSON(ORNL)
HEIR ERNST ALLARD SPANGLER SXTE TECH GAMMILL STEPP HUIPIAN SITE ANALYSIS VOLL1IHR BUNCH J,
COLLINS KRHGER CONTROL NUMBER tie ASLB
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89 EAST AVENUE, ROCHESTER, N.Y. 14649 R. R. KOPROWSKI VICE PRESIDENT TELEPHONE AREA COOE Tld 546-27'00 April 29, 1976 Director of Nuclear Reactor Regulation Attn:
Mr. Robert A. Purple, Chief Branch No.
1 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 t
Subject:
Main Steam'solation Valves R.E. Ginna Nuclear Power Plant Unit No.
1 Docket No. 50-244 Q
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Dear Mr. Purple:
The MSIVs installed at Ginna Station are 30 inch pipe
- size, 24 inch seat diameter, ANSI 600 lb. rating, Atwood and Morrill, swing disc type valves.
The existing valves have 25 1/4 inch diameter, carbon steel discs and disc arms.
The valves were analyzed for static differen-tial pressure loadings in accordance with the codes in effect. at the time of purchase.
The Ginna MSIVs have experienced several closures at full power with no damage to the valve discs or seats from the resulting dynamic loadings.
This is in reply to your request for additional information on main steam isolation valves (MSIVs). Initial reviews and analyses have been performed to provide the information requested.
The following are the results of these initial reviews and analyses:
E 1.
2.
Dynamic analyses have been performed by the valve manu-facturer for the type of MSIV installed at Ginna Station but of a larger size with stainless steel discs and disc arms.
The results of these analyses have been submitted to you previously.
(Joseph M. Parley Nuclear Plant, Final Safety Analysis Report, Appendix 10A, Amendment No. 45, Docket No. 50-348).
We have determined that if similar modifi-g'< cations are made at Ginna, the results of this analysis
~can be shown to be applicable to the Ginna MSIVs.
This will allow us,to provide you with the information requested and t the same time upgrade the design and material of the Ginna MSIVs.
ROCHESTER GAS AND ELECTRIC CORP.
April 2<,
1976 i~fr. robert A. Purple, Chief SHEET NO.
A purchase order has been placed for the new discs and disc arms, and they are scheduled for installation during the 1977 refueling outage.
An evaluation of these new discs and disc arms using the results of the analyses for the larger valves has been performed and is being reviewed at this time.
The results of this evaluation, in-cluding the information you requested, will be provided prior to installation of the new discs and disc arms.
Very truly yours, Robert R. Kopro ki RRK:cern