ML20107A567

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Requests Addl Info in Order to Complete Review of Rept, Preliminary Description & Analysis of Proposed Mods to Gaseous,Liquid & Solid Radwaste Treatment Sys for Oyster Creek Nuclear Generating Station
ML20107A567
Person / Time
Site: Oyster Creek
Issue date: 10/10/1973
From: Schemel R
US ATOMIC ENERGY COMMISSION (AEC)
To: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 NUDOCS 9604150024
Download: ML20107A567 (3)


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UNITED GTATES 9

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- ATOMIC ENERGY COMMISSION '

WASHINoTON, D.C. ' 20545 d

  • u October 10, 1973 Decke' No. 50-219 4

Jersey Central Power i Light Company ATTNt. Mr. I. R. Finfrock, Jr.

Vice President - Generation Madison. Avenue at Punch Bowl' Road Morristown, New Jersey 07960 Gentlemen:

By letter dated September 20, 1973, you submitted a report entitled

" Preliminary Description and Analysis of Proposed Modifications to the Gaseous, Liquid, and Solid Radioactive Waste Treatment Systems for Oyster Creek Nuclear Generating Station." In the course of our review of this

- submittal, we find that we require additional information to complete c,ur evaluation.

In order for us to complete an expeditious review of these proposed modi-fications, we request that you provide responses to the questions given J

in Attachment A by December 2, 1973.

Sincerely, i

4, 0

j obert J.

chemel, Chief

_ Operating Reactors Branch #1 Directorate of Licensing

Enclosure:

Attachment A - Request for Additional Information ec w/ enclosure:

G. F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge and Maoden 910 - 17th Street, N. W.

Washington, D. C.

20006 GPU Service Corporation ATTN:

Mr. Thomas M. Crimmins Safety & Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 See next page for add'1'cc Y

9604150024 960213 PDR FOIA DEKOK95-258 PDR _

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LJerseyLCentral Power & Light Company-October 10, 19731

.- t ec w/en' closure (con't):

Mr. Kenneth B. Walton Brigantine Tutoring 309 21st Street, S.

- Brigantine,.New Jersey 08203

.Miss Dorothy R. Horner Township' Clerk-

Township of Ocean 1 Waretown,-New Jeraey 08753

' 3urtis W. Horner Stryker, Tams and Dill 4 55 Madison Avenue

" Morristown, New Jersey ~ 7960 0

' Ocean County Library

-15 Hooper Avenue Toms Rivet, New-Jersey 08753 e

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ATTACHMENT A i

l REQUEST FOR ADDITIONAL INFORMATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 1.

It is proposed to design and construct the liquid waste system and the gaseous waste system to Quality Group D and non-seismic classification.

In this regard, discuss how the guidelines in Regulatory Guides 1.26 and 1.29 would be met for the accident conditions.

2.

Provide the weight of charcoal in each adsorber bed of the proposed gaseous waste system, the operating pressure of the beds, and the dyna-mic adsorption coefficient for the operating conditions of the beds.

3.

It is proposed to install the recombiners downstream of the delay line. State the reasons for the proposed installation location since it appears that installation of the recombiners chead of the delay line may be advantageous because it would provide for longer delay of j

the noble gases and eliminate the possibility of hydrogen explosions

'in the delay line.

4.

The Detergent and Laundry Waste Subsystem will utilize a detergent evaporator.

For this evaporator, provide the capacity, design tempera-ture, and design pressure.

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Jersey Central-Power & Light Company q

M ADisoN AVENUE AT PUNCH DoWL Ro AD e MoRRISToWN. N J. 07960 e 539-6116 1

October 9, 1973 A

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Mr. A. Giambusso Deputy Director for Reactor Projects d

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g Directorate of Licensing 1-4 United States Atomic Energy Commission

- -j h'ashington, D. C. 20545 pp.

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Dear Mr. Giambusso:

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Subject:

Oyster Creek Station Docket No. 50-219 loolation Condenser Relay Failure The purpose of this letter is to report a failure of isolation con-denser initiation relay 6K12. This event is considered to be an abnormal occur-rence as defined in the Technical Specifications, paragraph 1.15.D.

Notification of this event, as required by the Technical Specifications, paragraph 6.6.2.a.,

was made to AEC. Region I, Directorate of Re'gulatory Operations, by telephone on September 29, 1973, and by telecopier on October 1, 1973.

h'hile performing a routine surveillance test on the reactor high pres-sure - isolation condenser initiation switches, contacts on relay 6K12 failed to close within the preset time delay of 15 seconds after tripping the pressure switch and doenergizing the relay.

Details of the relay are:

Manufacturer: Agas tat Model:

7022PDT (Time Delay)

Range:

5 to 50 seconds Coll:

120V DC Serial No.:

1712236 The cause of this failure remains unknown. The relay has been removed from the circuit and bench-tested and appears to function properly, even after rc-pented operation.

i Relay 6K12 was replaced with a new relay.

A satisfactory surveillance test was conducted and the isolation condenser system then considered to be.

-operabic.

'As detailed in Amendment 65 to the FDSAR, at least one of the isolation condensers is required to act as a means for heat removal during a postulued loss of coalant accident.

Actuation of relay 6K12 can be by.means of high reactor y0 w

mo y an 2,,.

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Mr. G).anbusso October 9, 1973 pressure or low-low reactor water level.

It is wired into the logic circuit

.such that tripping of the relay provides one-half a the initiation logic for both condensors, the other one-half being its redundant counterpart on the same instrument penetration.

A second redundant instrument penetration also includes two pressure switches, contacts from which also will initiate both isolation condensers. The significance of this event then is the loss of redundancy pro-vided to initiate'one-half of the signal for placing the isolation condenser system in service.

Before making any recommendation to prevent a reoccurrence of this event, the cause of the relay failure should be identified. The manufacturer will be requested to perform additional tests on the failed relay in an effort to determine the cause of failure. The results of this investigation will be used to determine what further action may be necessary.

Enclosed are forty (40) copies of this report.

Very truly yours, Y

Donald A. Ross Manager, Nuclear Generating Stations DAR:es Enclosures

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cc:

Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region I l

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