ML20151C182

Forwards AO Status Rept on Followup to Recommendations. Response to 721218 Request for Evaluation of Consequences of Pipe Failures Outside Containment Structure Will Be Submitted by 731008.Requests Meeting to Discuss AO Items

ML20151C182
Person / Time
Site:	Oyster Creek
Issue date:	08/30/1973
From:	Finfrock J JERSEY CENTRAL POWER & LIGHT CO.
To:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8103040976
Download: ML20151C182 (8)

Text

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>. frqn Jersey Central Po3 1 & Light Company

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M Aol$oN AVENU E AT PUNCH BOWL Ro AD e MoRRISToWN,. N.J. 07960 e 539 6111 y'y 1 N+ 8M+m 'e August 30, 1973 SEP $ 973 { y 9_ _ ,

" = Eumn & K k m n: o:r Mr. Donald J. Skovholt jg -\

Assistant Director for & jg v j Operating Reactors 7  :

Directorate of Licensing (

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. Washington, DC 20545 , . .

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O ' I ' $y '- \, -

Dear Mr. Skovholt*

SUBJECT:

OYSTER CPEEK NUCLEAR GENERATING STATION DOCKET 50-219 OUISTANDING LICENSING ITEMS This is to inform you of the status of various outstanding licensing items and the revised submittal schedule for these items.

With regard to the recommendations made in conjunction with the filing of Abnormal Occurrence Reports, the attached report summarizes the status of follow-up efforts which have not been previously reported to the Commission. In addition, a discussion of the Electromatic Relief Valve Discharge Piping Restraints is included.

Your letter dated December 18, 1972 requected an evaluation of the consequences of pipe failures outside of the containment structure. Although our original estimated submittal date was April 27, 1973, this project has resulted in the need for a larger commitment of time and manpower than originally anticipated. It is expected that a submittal can be made by October 8,1973.

Delays have been encountered in compiling the information necessary to respond to your January 22, 1973 letter on Drywell Vacuum Breakers and your April 3, 1973 letter on Main Steam Isolation Ve lve s . We are expecting to make a partial information submittal THIS DOCUMENT CONTAINS P0OR QUAL.lTY PAGES ggg

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n Mr. Donald J. Skovholt Page 2 on October 1,1973 for each of these items. A date for submittal of  :

the remaining information vill be given at that time.

We would like to request a meeting with you, at your convenience, to discuss other outetanding items and a schedule for their submittal.

Very truly yours,

o b Ed?7 .'h;2 [

Ivan R. Fin rock, Jr.

Vice PresiIfent #

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August- 31, 1973 t

ABNOPN.L OCCURRENCES s -

STATUS REPORT ON 1

FOLLOW UP TO IlECOFC-1ENDATIONS

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1. F2in Steam _ Isolation Valve! Cushion, Spud Failure (EE: Decccher 14, 1971 letter JCPhL to AEC)

The manuf acturer was contacted and several samples of the failed cushion spud vere sent to their plant for analysis. Cheuical and micro-scopic testo verified that the material met the specificationc. liydro-Line also reported that thousan's d of units similar to our cylinders are

. giving satisf actory service in more. savere applications. Several causes for the f ailure were hypothesized by liydro-Line, but no conclucive evidence is available to substantiate the postulated causes for fai3ure.

During the April-May 3972 refueling outage ,all four cushion spuds vere dye-pene trcnt examined and found ' to be in good condition. Durin g the sane outcre, the rod and cushion spud in 5503n's oparator vere replaced with n rod which required no cuchien vpud. During the spring 1973 refneling outage, the rods of the three other ITISVs vere niso replaced uith the new type rod. -

2. Diesel Generator Louver. Failure (RE: June 30, 1972 letter JCP&L to AEC) ,

. The manuf acturer (General Motorc) was contacted for recommendations to prevent this type of failure in the future. The recomnended modifi-cariens supplicd by Genercl Motors, hewever, were not incorporated since they would unnecessarily complicate the Leuver control systen. Plant engineering personnel have recently proposed a nodification which Jncorpo-rates redundan t Louver control temperature switches. This propcsed modification vill be forwarded to the manufacturer for approval prior to revier by the P.lant Operations Reviev Connittee and the Gencral Office Revier Bocrd.

3. Isolation Condenser Failure (RE: August 22, 1972; April 24, 1973 Jetters JCP&L to ALC)

A. The snubbers from the instrument header sensing lines were relocated to the individual sensing line connection for each dif ferential pressure instrument (both isolatien condenscrs)

. during August, 1972. This permits flow testing of the as-sociated excess flow check valves free from the effects of any snubber.

I E. The "B" isolation condenser condensate return valve V-14-35 subsequently f ailed to cpen on Decenber 29, 1972 as reported to Mr. A. Gladbusso in a Jetter dated January 19, 1973 from Mr. D. A. Roos. V-14-35 a;;nin f ailed to open in April, 1973 as reported to Mr. /.. Giaebusso in a letter dated April 24, 1973 from Mr. D. A. Ross. Repairs tc V-14-35 were completed during the 1973 refueling outage.

The cause for the failure of the Isolatica Condenser NE01B Condensate Return Valve, V-14-35, to open unnually was traced to the design of the valve to be installed with 91 ,e +e- --,r--, *---4 yy-,,v , ,-,em,e ,,m n.yeq..- +.--,,--r -c , ,w.,-v , , - . ,..,--e- - + . r - , e w-

the sten vertical, but the valve is in the horizontal pocition vith the stem travel horizontal. The valve dice guides are rough cact, off center, tapered outward toward the bonnet and have a seat ring tool relief in the water-vay. The smallest distance between the guides is 10.400 inches. The disc was tested in the valve by pushing it in and out with the stem installed. As the dice reached the

. narrouest. point between the guides, it rode onto the re-lieved portion and dropped. down with a rotating motion.

Contact is made betveen the upper guide and the disc. The disc continues into the closed position. The disc cannot be removed by pulling straight out with the stem. Ilowever, it can be rocked out encily.

The repair' of the valve consisted of adding veld .

. build-up to the lower guide so ac to give the disc a horizontal run into the valve, therefore, preventing the disc from rotating and locking into the body. The disc was then rctested sat.icfactorily. In addition, the valve has operated normally during subsequent survc111cuce testing.

4. Lackup Scran Eolenoid (RE: September 26,,1972 letter JCP&L to AEC)

Ucu "0" ring scals were installed on the leaking scram pilot solenoids and the backup scram solenoids on December 31, 1972 to pre-vent recurrence of this event.

In cddition, General Electric Company has presented a proposed mocification to the backup scraa solenoid piping. This proposal vill be forwarded to the Plant Operations Review Committee and the General Office neview Board.

5. Electromatic Relief Valve Discharge Piping Restraints Since the relief valve failure at Turkey Point on December 2, 1971, Jercey Central Power and Light Company has been reviewing the decign of the Electromatic Relief Valvc inlet and Discharge Piping in both the Dryvell and Torus. Bcced on thic revicu, there have been three successive modifications. At this time, the transient and steady state stress conditions have been analyzed (and re<luced where necessary by means of' modification) at cach point in the clactromatic relief valve system.

The result of these ruodifications has been to reduce the stress at all points, under all conditions, to levels within the allowabic stresses of USAS B31.1 (The original code used for the electronatic relief valve system design). .

Figure VII-1 is an isometric of the south header and the system of hangers and restraintc that were installed during the different phases of the ptoject. Likevice, Tigure VII-2 is an isomatric of the north header and its restraiutc and hangers.

The major modification accon:plished during the Spring 1973

shutdown was to remove the temporary cables on the Torus canal fittings and install pcreanent rentraints to recolve both vertical.and horicontal stress. The temporary installation was completed during August 1972 and reported in a lettcr fron Mr. I. R. Finfrock, Jr. , to Mr. D. J. Skoviolt, dated August 22, 1973, and the six month report for July-December 1972. In addition to the Torus installation, an ad-ditional restraint was installed on the south header at the 14" to 12" reducer to help reduce the stress at the 8" to 14" lateral.

I Finally, a spring hanger on the 8" line of the south header was repicced with a stronger one to reduce stress on the came lateral mentioned above.

The remaining hangers and restrainto chown on Figure VI-1 and -2 wcr installed during May 1972 and reported in both the January-June 1972 l oix-month report and the letter ref erenced above.

Safety Analycir: Ac previously diccucsed, the purpose of the modificetion was to reduce all stresses, both transient and steady state, l

to a level, at all pointe in the electromatic relief valve system, l within the code requirements of USAS B31.1 This was the original code l

with which the syctem was decinned. The modification did cecomplish I the objectives and, therefore, results in the following conclusions:

I 1 A. The probability of the occurrence of an accident or equipment nalfunction is not significantly increased. In fact, the addition of the piping supports reduced the chances of an accident occurring.

B. s The consequences of an accident or malfunction of equip-cent are not 1ncreased due to the codification. If a discharge i pipe failed, the steam would enter the drywell or torus in the same canner with or without the supports installed.

j C. There is no possibility that an accident, of a different l

type other than the type that has been previously evaluated ,

has been created by this modificctien. .

D. The margin of safety of the relief valve discharge piping ,

has not been reduced. In fact, as stated in 1. above, the ad-dition of the piping supports increases the system safety margin.

For the above reasons, an unrevicwed safety question does not exist.

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