ML20084J248

AO-73-14:on 730723,plot of Absorption Pool (Torus) Water Level Developed.Caused by Feedwater Leak Around Check Valve Hinge Pin Seal Plugs.Erosion of Seating Surface on Valve Body Machined Out

ML20084J248
Person / Time
Site:	Oyster Creek
Issue date:	07/31/1973
From:	Carroll J, Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Anthony Giambusso, James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), US ATOMIC ENERGY COMMISSION (AEC)
References
AO-73-14, NUDOCS 8305120271
Download: ML20084J248 (10)

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M ADISoN AVENU E AT PUNCH BOWL Ro Ao e MoRRISToWN. N.J. 07960 e 539-6111 July 31, 1973 w

x

,ps Mr. A. Giambusso 0

Deputy Director for Reactor Projects gjg 0

,9 Directorate of Licensing g-g y

/S / 3 g United States Atomic Energy Commission t h, % r h

Washington, D. C. 20545 g

Dear Mr. Giambusso:

Y s

Subject:

Oyster Creek Station Docket No. 50-219 Reactor Coolant System Leakage The purpose of this letter is to report a violation of the Technical Specifications,' Paragraph 3.3.D., " Reactor Coolant System Leakage". Operation of the reactor at power continued when it was not recognized that an increasing l

absorption pool level, combined with the rate of leakage into the drywell sump, originated from the same source and thdreby resulted in an " unexplained" leak rate in excess of 5.0 gpm. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, Paragraph 1.15.B.

Notification of this event as required by the Technical Specifications, Paragraph 6.6.2.a., was made to AEC Region I, Directorate of Regulatory Operations on Monday, July 23, 1973.

As indicated in Figure 1, attached, an increasing rate of Icakage into the drywell sump began to occur on July 1,1973 and continued through July 19, 1973, reaching a peak of approximately 3.92 gpm when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As shown in Figure 2, attached, a plot of absorption pool (torus) water level devel-oped on July 23, 1973 over the same period indicated the level to be increasing starting about July 11, 1973.

It is now estimated that the unexplained leak rate increased to >5.0 gpm at some time during JLly 17, 1973 and continued to be above the 5.0 gpm limit until the plant was shut (lown and depressurized on July 21, 1973.

The source of this leakage was found to be a f.cedwater check valve hinge pin seal plug, which due to its position and the manner in which the water

.:as spraying out, resulted in Icakage to both the drywell' floor and the torus.

Valve data is as follows:

Manufacturer: Anchor Valve Company Type:

18",- 600# Swing Check Valve Material:

Cast Carbon Steel - Stallit' Trim BW Ends 8305120271 730731 gDRADOCK05MO

(

5940 1

COPY SENT REGION

Mr. Giambusso July 31, 1973 A

In order to repair this seal, the erosion of the seating surface on the valve body was machined out and the plug adapted to fit using a procedure

' developed by MPR Associates and concurred in by the valve manufacturer and the -

PORC.

In addition, a calculation was performed which verified that after machin-ing, the valve wall thickness was still satisfactory.

A successful leak test was conducted on July 24, 1973 and the plant returned to service.

The a110wable leakage rates of coolant from the reactor system are based in part on predicted and experimentally observed behavior of cracks in.

pipes.

As noted in the basis of the Technical Specifications, "... evidence suggests that the leakage somewhat greater than the limit specified or un-identified leakage, the probability is small that imperfections or cracks associated with such leakage would grow rapidly." The Technical Specifications limit re-ferred to in the above is 5.0 gpm; whereas, in this instance, the maximum leak rate approach is 6.75 gpm.

Since the source of leakage in this case was a gasketed seal, no undo safety significance need be associated with this event.

The possibility of the drywell sump under unusual circumstances not identifying the total unidentified drywell Icakage must be recognized.

To prevent a reoccurrence of this type event, Procedure 515.3, "Small 3

Piping Leaks in Drywell" will be revised to recognize that in cases where the torus water level is increasing and the Icakage source cannot be identified, this inleakage will be added to the drywell unidentified leakage.

Enclosed are forty (40) copies of this report.

Very truly yours,

/

.) V Donald A. Ross Manager, Nuclear Generating Stations DAR:cs i

f Enclosures cc:

Mr. J. P. O'Reilly, Director Directorate of Regulatory Cgerations, Region I t

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o-o s-Tot James P. O'Reilly Directorate of Regulatory Operations Region I 970 Broad Street Newarko New Jersey 07102 Frong Jeracy Central Power & Light Company Cyster Crook fluclear Generating Station Docket # 50-219 Torked River, New Jersey 09731 Subjcct Abnorcul Occurrence Report 73-14 The following is a prelltninary report belny submitted in compliance with the Technical Specifications paragraph 6.6.2 Preliminary Approvalt h *l Attdl 1/24/13 J. T. Carrolle Jr. f Date cct Mr. A. Giambusso

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Abnormal Occurrence Report No. 73-14 SUBJ5CTt Violation of the Technical Specification'a paragraph 3.3D, Reactor Coolant System teakage. Operation of the reactor at power continued when it was not recognized that an increasing Absorption Pool Level combined with the rate of leakage into the Dr*)well Sump resulted in an " unexplained" leak rate in excess of $ gpm.

9 This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.168.

Notification of this 4

event as requirod by tha Technical Specifications, paragraph 6.6.2a, was made to AEC Region I, Directorate of Regulatorg Operations by telephone on Monday, July 23,1973, at 4:20 p.m., and by telecopier on Tuesday, July 24,1973 at SITUATION:

As indicated in Figure to attached, an increasing rato of leakage into the Drywell Sump began to occur on July 1,1973 and continued through July 19, 1973, reaching a peak of approximately 3.92 gym when averaged over 24 1

hours. As shown in Figure 2, attached, a plot of Absorption Pool (Torus) water loval daveloped on July 23, 1973 over the saneperiod indicated the level to be increasing starting about July 11, 1973. It is' now

• estimated that the unexplained leak ratel. increased to >S.0 gpm at some tima during July 17, 1973 and continued to be above the S.O gpm limit until the plant was shutdown and depressurized on July 21, 1973.

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• s 2-I CAUSRt The cause was found to be a fced water leak around one of the feed-water check valva hingc pin seal plugs, which due to its position and the manner in which the water was spraying, resulted in leakage to both the Drywell floor and the Torus.

Valvo data is as follows:

Manufactutor: Anchor Valvo Company Typor 18" - 600H Swing Chack Valve P. S.

Materiait Cast Carbon Steel - Ste111tc Trim BW ends REMEDIAT. ACTIQV:

The crosion pf the saating surface on the valve body was enachined out, minimum wall thicknoss checked to be satisfactory, and the plug adapted to fit. A successful leak test was conducted at operating picssure on and the plant returned to servico.

SAFETY SIGt/IFICNICRt N

The allowable leakage ratcs 'of coolant from tha reactor system are based in part on predicted and experimentally observed behavior of cracks.in pipas. As noted in the bases of the Technical Spacifica-tions, "... ovidence suggests that for leakage somcwhat greater than the limit specified for unidentifled leakage, the probability is small that imperfections or cracks associated with such icekago would grow rapidly."

The Technical Specification limit referred to in tha above is S.O gpm) whereas, in this instanco, the maxic:um leak rato approach G.7S gpm of which u 1.0 gpm might be considered"nornal." Thus, the leakage around the hinga pin plug was on,the ordar' of 5.5-6.Q.gpm and consequently no. undo.

significance need be attached to this event.

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Jer Central Power & Light Company I

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!!. D. Thornburg, oAic Docket No.:

50-219 Chief, FS&EB

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Abnormal Occurrence:

73-14 1i s

70 (Na,re and unio IMil, A1.5 RtMARKS l

RO:ilQ (5) l DR Central Files (1)

The attached report from the subject licensee is oAlt Regulatory Standards

3) 7

.1, Dir. of Licensing (131 forvarded in accordanen with no Manual Chanter 1r '.i 10 (rdame and un shillALS RLMARKS RO Files Central Ma'l & Files The action taken by the li_censee is considered i

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mn appropriate.

Followup will be performed during

,I the next insnection a's appronri. ate.

Confessof l9 F ROM (Name and un.t)

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the report have been foruard?d to the PDR, Local i

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R. T. Carlson, Chief PDR, NSIC, DTIE and State representatives. The

. Facility Operation Branch licensee will submit a 10 day written report to PHQht M CATE 8/6/63 Licensing.

USE OTHER LICE FOR ACD&TIONAL REMARK.S CPO : 1,11 C. 445- <

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