ML19095A608

Submit Licensee Event Report No. USRE-S1-76-08 Re 1928 Ppm Boron During Normal Operation Routine Sample of B Safety Injection Accumulator

ML19095A608
Person / Time
Site:	Surry
Issue date:	07/30/1976
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/RGN-II
References
Serial No. 162 LER 1976-008-00
Download: ML19095A608 (4)

Text

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e VIRGINIA ELECTRIC .A.ND POWER COMPANY RICHMOND, VIRGINIA 2 3 2 61 July 30, 1976 Mr. Norman c. Moseley, Director Serial No. 162 Office of Inspection and Enforcement PO&M/ALH: j lf

u. s. Nuclear Regulatory Conunission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moseley:

~Pursuant to Surry Power Station Technical Specification 6.6.2, the Virginia Electric and Power Company hereby submits a copy of Licensee Event Report No. USRE-Sl-76-08.

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Conunittee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Conunittee.

Very truly yours, Vice and Enclosure cc: Mr. Robert w. Reid, Chief (40 copies)

Operating Reactors Branch 4

USRE-Sl-76-08

. .ICENSEE EVENT REPORT

• • CONTROL *BLOCK: I I. I .,, ,. I *I . (PL,$E PRINT ALL REQUIRED INFOAMA!ION)

.., 1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

@EJ 7 8 9 Iv IA Is I PI sI 14 1 I 15.. lo lo l*-Lo lo lo I oI ol-'-la.loJ 25

.I264 I 1 l 1 11 I o30I Io31 I 332I REPORT REPORT CATEGORY REPORT CATE w w .I TYPE SOURCE DOCKET NUMBER EVENT DATE

@El coN'T I pt o! O I 5 lo. I ~ I O I 2 I 8 I 'O68I I690*1 i I al 2 I1 ! 674I !ol1!2!1!1t6!

7 B 57 58

• 59 60 61 75 80 EVENT DESCRIPTION

[§lg] !During normal operation a routine sample of "B" safety_inject:i,9n.. acsurnlator indicated!

7 B 9 . . BO 7

loj3j !1928 ppm boron, which is contrary to the Technical Speci.fication 3.3.A.2 limit of 1950 8 9 . . , . . - - - ._-.-,.,...-----------------,.-----8-,".0 j

[oj4j I*ppm~ The* accumulal:or was recirculat1=d with the RWST to increase the boron concentra.;. j 7 89 . ~

@el Ltio~ above 1950 )pm. This .e.vent is reportable per Technical ~pecificatioti 6.p. 2. b(l) I 7 8 9 80 filNJ

7. 8 9 L__ (USRE-Sl-7 6-08!..-)* - - - , - . . , - - - - - - - , - - - - - - - - - - . . . , ; . - - , - - - - - - - - - - - - - - - - - - - '

. . PRIME BO

. SYSTEM * , CAUSE ,.;COMPONENT COMPONENT CODE COOE COMPONENT COOE SUPPLIER MANUFACTURER VOLATION 7

@£1 B 9 IP 10!c I* *L!J I VI A I LI ~ E I X17I uJ 43 10 1012 Lo 47I L!J.

11 12 44 48.

CAUSE DESCRIPTION 7

loJ0j8 *9lcheck. ~alves .

1-SI-128, and 1-SI-130 were found to be.leaking bv and diluting the

.. I

. 80

• @Jfil laccunrulator boron, concentration from the "B" primary loop. The sample frequency of the I 7 .B 9 ... * . . . . 80

[I@]  !accumulator was increased to weekly. The dilut.ion rate of the accumulator (continued)~

7 8 9 . . . . . . 80 FACILITY METHOO OF STATUS  % POWER OTHER STATUS DISCOVERY OISCOVERY DESCRIPTION

EE]

7 8 9 w 10 It .:o Io 12I jN/A 44 l!.J 45 46 IN/A 80

.FORM OF ACTIVITY CONTENT I I rn w RELEASED . OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

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10

. N/A 1-1-------------------,144

. N/A .I 7 8 9 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

[el lo Io *I oI LI] --.N......A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____,_ _ _ _ _ ___,

7 8 9 11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTION.

7fiEJlololol as

• 11 1".'-2__NA....__ _ _ _ _ _ _ _ _ _ _ _ _--,_____________________________..__J OFFSITE CONSEQUENCES 7

rn 8 9 NA LOSS OR DAMAGE TO FACILITY

• TYPE DESCRIPTION 7

[!E}s* s~ '!e-~N~A=-~~~~~~-----~~~~~~~~~~~~~~--~~~

10 PUBLICITY (ill] . N/A i I

7 8 9 80 ADDITIONAL FACTORS

~ !The accumulator was isolated for a period less than four hours, therefore the unit I 7 8 9 . 80 EJfil !did not require a power rampdown per Technical Specification 3.3.B. I

7. B 9 80 NAME: _ _ T__._L_._B_a_u_c_o_m__________________ PHONE: ( 804) 357-3184

,., r _.. ",

CAUSE DESCRIPTION (CONTINUED) is monitored and the accumulator recirculated with the RWST when necessary.

During. the upcoming refueling outage the check valves will be repaired.

The total effect of this boric acid dilution would not have affected shutdown capability at this point in core life. A safety injection would have placed the plant in the cold shutdown ~ondition despite the reduced boron concentration in the accumulator.

Since the safety injection system maintained its capabilities, the health and safety of the general public are not affected.

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