ML19031A762

LER 1976-020-01 for Salem, Unit 1 High Reactor Coolant System Chlorides

ML19031A762
Person / Time
Site:	Salem
Issue date:	01/14/1977
From:	Schneider F Public Service Electric & Gas Co
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1976-020-01
Download: ML19031A762 (5)

Text

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Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark. f\l.J. 07101

• 201/622-7000 Vice Pres,der.t Production January 14, 1977 Mr. James P. O'Reilly Director of USNRC Off ice of Inspections and Enforcements Region I 631 Park Avenue King of Pruss~a, Pennsylvania

• 19406

Dear Mr. O'Reilly:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 76-20/3L Pursuant to the requirements of Salem Generating Station Unit

• No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 76-20/3L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, CC: Director, Office of Inspection and Enforcement (40 copies)

Director, Office of Management Information and Program Control

( 3 copies)

Report Number:

Report Date:

Occurrence Date:

Facility:

.-_ 76-9-'3L 1/3/77 12/7/76 Salem Generating Station Public *service Electric & Gas Company Hancock's Bridge, New Jersey 08038*

IDENTIFICATION OF OCCURRENCE:

High .Reactor Coolant System Chlorides CONDITIONS PRIOR TO OCCURRENCE:

Operational Mode 3 P~ant Pressure 2235 psig Plant Temperature 540°F DESCRIPTION OF OCCURRENCE:

On 12/7/76 at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, the Performance Department informed the Shift

• Supervisor that the results of the Reactor Coolant System Chloride Analysis was 0.17 ppm. Being above the allowable Technical Specification Steady Si;".ate limit of 0.15 ppm Cl-, the Shift Supervisor implemented Technical Specification Action Statement 3.4.7 (a). The Performance Department continued to take chloride samples. No. 12 Mixed Bed Demineralizer was placed in service, No. 11 Mixed Bed Demineralizer was removed from service. On 12/8/76 (1600-2400 shift), the Reactor Coolant System chloride samples were within the Technical Specification limit. The Technical Specification Action Statement was cancelled.

DESIGNATION OF APPARENT CAUSE OF' OCCURRENCE:

The Boric Acid Storage Tank, which_had a chloride concentration near the upper limit (limit 0.15 ppm Cl),. was used to refill the Boron Inj ectin:n. Tar..k. The Boron Injection Tank was injected into the Reactor

• Coolant System four . (4) times due to inadvertent safety injection actuation which would have increased the chloride concentration but this determination is inconclusive due to the difficulty in achieving accurate chloride analysis in a boric acid solution. When 20,000 ppm boric acid solut".i.on is diluted to 5,0QO ppm boric acid, the dilut;!;on factor of 4 must be applied to the Cl endpoint. ~ny error in Cl titration endpoint is amplified by the application of the dilution factor~

ANALYSIS OF OCCURRENCE:

An Engineering,evaluation was performed by Westinghouse to determine the effects of the out of specification chloride condition in regard to the structural integrity of the Reactor Coolant System. The evaluation concluded that a chloride concentration of 0.3 ppm for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would not cause any adverse effect to the Reactor Coolant System. Based on the RCS chloride concentration which was 0.17 ppm in regard to the Engineering evaluation performed assuming 0.3 ppm Cl- for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, no corrective action is proposed for the Reactor Coolant System. At no time was there any danger to the health and safety of the public or site personnel.

LER 76-20/3L CORRECTIVE ACTION:

No. ll Mixed Bed was removed from service to determine whether or*not

. chlorides were being leached off the bed into the reactor coolant*. Both Mixed Beds were found to be performing satisfactorily. *The chemistry procedure for chloride determination by titration will be reviewed and revised as necessary to improve the "endpoint" determination.. Laboratory personnel will be reinstructed on the methods and techniques described in the procedure to visually determine the titration "endpoint". The Public Service Energy Laboratory will attempt.to develop a better pro-cedure for chloride analysis. The Westinghouse analysis of the problem determined there were no detrimental effects to the structural integrity ot the reactor coolant system. Follow up analyses indicate chlorides in the reactor coolant system to be well within specifications.

FAILURE DATA:

This is the first occurrence of this type. Equipment identification not

• . applicable.

I Prepared by B. Canfield

• ..~1);~12u1._/

, lr0 ~;1 * /

Manager - plem Generating Station

.SORC Meeting 3-77

LICENSEE EVENT REPORT.

CONTROl. !!LOC)( I 6

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50 1015101-101217121 s1 e.a 1112101717161 69 74 10111013!7t7J 75 EVENT OESCRIPTION

@liI I During Mode 3 operation, the Performance Department 1.

1

@))I 89 (Chemistry) informed the Shift Supervisor that the results ro J

1 8 9

@El I of the reactor co.olant system sample anavlsis was 0 .17 ppm.

7 8 9 J

' @:fill Being above the allowable Technical Specification limit of I 1 a9 ao

~I 0.15 ppm,- the Shift Supervisor implemented (see attached) I" 7 a 9 . . PRIME ao SVSTEM c..=.use: COMPONENT COMPONENT

. COCE cooe: COMPONENT cooe SUF'Pl..IER MANUPACTUR!::R . VIOl.ATlON

@TI] t Cl BI L!J IZ I Z I Z I Z I ~ LE.J I ZI 9 I 9 I 9 I lliJ 1 s 9 10 11 12 17 43 44 47 48 CAUSE OESCl'llPTION

~I The Boric Acid Storage Tank chloride reading was near the I

@mi9 limit which was used to fill the Boron Injection Tank. The j 1 ag ea

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Reportable Occurrence 76-20/3L Licensee Event Report Page (2)

EVENT DESCRIPTION (Continued)

Technical Specification Action Statement 3.4.7 (a). The Performance Department continued to t&ke additional samples. No. 11 Mixed Bed Demineraliz~r was taken out of service and No. 12 Mixed Bed Demineral-izer was placed in service. On 12/8/76 (4 PM ~ 12 PM shift), sample results were in specification. Technical Specification Action State-rnent was cancelled. Redundant system availability is not applicable for this occurrence. This is the first occurrence of this type (76-20/3L).

CAUSE DESCRIPTION (Continued)

Reactor Coolant System four times due to.inadvertent safety injection actuation which could have resulted in the increased chloride concert-tration, but this cannot be conclusive due to the ,difficulty to achieve accurate chloride sample analysis in a boric acid solution by the method of mercuric titration. When a 20,000 ppm boric acid sample is diluted to 5,000 ppm to titrate for chlorides, any error i!f determining this epdpoint is multiplied by the original dilution ratio (4 to 1). Also, consistent results are difficult to achieve when the.boron concentration changes. Hydrazine and ammonia analyses were performed on No. 11 Mixed Bed Demineralizer which verified no inter-reaction occurred to produce chlorides.

Manufacturers nameplate data not applicable for this occurrence.