ML18143A965
| ML18143A965 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/01/1976 |
| From: | White L Rochester Gas & Electric Corp |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18143A965 (5) | |
Text
U.S. NUCLEAR REGULATORY CO"'MISSION NRC FORM 195 (2-16)
NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL DOCKET NUMBER 5o-a44 FILE NUMBER TO:
MR K GOLLER r-.ROM:
RGE ROCHESTER'-'NY DATE OF DOCUMENT 4-23-76 LETTER RIG INAL OPY DESCRIPTION
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0 N0TO R IZ E D UNCLASSIFIED P ROP L D WHITE, JR.....
INPUT FORM ENCLOSURE DATE RECEIVED 5-1-7 NUMBER OF COPIES RECEIVED 1 SIGNED......
LTR REF M OUR 10-1-73 LTR.....FURNISHING RESULTS OF INSPECTION OF HYDRAULIC SHOCK ABSORHERS AT R E'INNA NUCLEAR POWER LANTo
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P ACKNO~@D PLANT NAME R E GINNAgl,...
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SAFETY ASSIGNED AD:
FOR ACTION/INFORMATION ASSIGNED AD:
ENVIRO BRANCH CHIEF:
PROJECT MANAGER:
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SST BRANCH CHIEF
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PROJECT MANAGER.
LIC~ ASST, FILE NRC PDR I & E GOSSICK & STAFF AS EN NEE KNIGHT SIHWEIL PAWLICKI INTERNALDISTRI BUTION BENAROYA IPPOLITO OPERATING REACTORS STELLO OPERATING TECH ERNST ALLARD SPANGLER SITE TECH GAMMILL'TEPP H
N PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION EISENHUT SHAO BAER SCHWENCER GRIiKS SITE SAFETY & E R
ANALYSIS DENTON & HULLER SITE ANALYSIS VOLLMER BUNCH J,
COLLINS KREGER CONTROL NUMBER LPD TIC NS ASLB c.T-R NATL LAB REG, V-IE LA PDR CONSULTANTS BROOKHAVEN NATL LAB ULRIKSON(ORNL) 4211 NRC FOAM 196 (2.76)
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ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE. JR,
""""""FItgujatory, DOCkei, fLjje.
TSI.SPHoN Director of Nuclear Reactor Regulati ATT¹ Mr. Karl Goller Assistant Director for Operat'pg Reag Division of Operating Reactors-'<
U. S. Nuclear Regulatory Commission
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Washington, D. C.
20555
Subject:
Inspection of Hydraulic Shock Absorbers (Snubbers)
R. E. Ginna Nuclear Power Plant, Unit No.
1 Docket No. 50-244
Dear Mr. Goller:
In accordance with Mr. Skovholt's letter of October 1, 1973, con-cerning periodic inspection of hydraulic shock absorbers (snubbers),
an inspection of all snubbers both inside and outside of containment was conducted during the spring 1976 refueling shutdown.
All units were found to be operable at unit shutdown; however, frequent fluid additions were necessary on the reservoir to the 1A steam generator hydraulic restraints.
During the shutdown a Bergen Paterson unit located on the B main steam line was noted to have an accumulator leak.
The accumulator was removed and the seals were replaced.
The accumulator piston seal was found to be scored.
This was the only safety related pipe restraint that required maintenance.
Also during the shutdown the Anker-Holth snubbers for the "A" steam generator were inspected with a vendor's representative.
The snubbers and filltubing were pressurized to 1500 psig and checked for fluid leakage.
The hydraulic units tested satisfactorily; however, several leaks were found at 3/8" tubing fittings in the fluid addition lines to the units and these were corrected by tightening.
Following heat up leakage was again noticed from the "A" steam generator units.
Scaffolding was erected under the suspect units and one unit was found to have a shaft seal leak at the outboard piston shaft.
Cause of seal leak was a damaged backup washer that had extruded into the seal area and damaged the seal.
After repairs the unit was pressure tested to ensure unit tightness.
The physical condition of the other seals and the internals of the unit appeared excellent.
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ROCHESTER GAS AND ELECTRI RP.
, pATE,April 23, 1976 To Director of Nuclear Reactor Regulation ATTN: Mr. Karl Goller SHEET NO.
2 Allunits were again inspected on April 13, 1976 with the plant at power.
There was no indication of leakage from any units.
Very truly yours',
~.p, L. D. White, Jr.
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