ML18152B071

LER 88-027-00:on 880714,Tech Spec That Required Sampling Had Not Been Performed within Required Time Frame.Caused by Step 3 of Svc Water Contamination Analysis Procedure Being Performed on Old Data.Samples obtained.W/880803 Ltr

ML18152B071
Person / Time
Site:	Surry
Issue date:	08/03/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-035, 88-35, LER-88-027, LER-88-27, NUDOCS 8808150414
Download: ML18152B071 (4)

Text

POW 28-06-01

\

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED 0MB NO. 3150-0104 LICENSEE EVENT REPORT (LERI EXPIRES: 8/31/88 FACILITY NAME 111 DOCKET NUMBER (2) PAGE 131 Surry Power Station, Unit 1 I o 1s 101010121810 1 loF 01 3 TITLE 141 Missed Surveillance Due to Personnel Error EVENT DATE (51 LEA NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR  :::::::::: SEQUENTIAL I:{:{: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI

NUMBER ~:::;:::::: NUMBER o 17 1 I4 s s 8 1s - o J2 J7 - oIo o I8 o 13 8 1s THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more of the follol'(ing) (11)

OPERATING MODE (9) N 20.402(b) 20.405(c) 50.73(a)l2)1iv) 73.711b)

I

- - - -.........- -.......- t - - - i - ,_ -

POWER 20.405(0)11)(1)

- 50.36(c)(1) 50.73(o)l2)1v)

- 73.71(c)

L71~~L O IO I O - 20.405(,)(1)(iil

-X 50.36(c)(2) 50.73(a)(2)1i) -- 50.73(*) (2)(vii) 50.73(a)(2)1viiillA)

- OTHER (Specify in Abstract b~low and in Text, NRC Form 366A) 11111111111111111111= :::::::::~:

60.73(a)l2)1ii) 50.73(a) (2) (iii)

LICENSEE CONTACT FOR THIS LEA (12)

- 50.731*) (2) (viii) (B) 50,73(a)(2Hxl NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I 014 3 1517 1-1311 1814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPONENT MANUFAC* REPORTABLE::::**.* .. *.*::::>*****.*.**-::::::::::: CAUSE SYSTEM COMPONENT MANUFAC-TURER TO NPRDS .*,.*.*.*.*.*.*.*.*.*.:.*.*.*.*,,... *.*.*.*:*:*.* TURER I I I I I I I I I I I I I I 11 1 1 11 I I I I I I I :jJ i:!l li!ilii iililililii!illlii i 1i i i iiiiii I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED

---i YES (If yes, comp/ate EXPECTED SUBMISSION DA TE/

ABSTRACT (Limit to 1400 spaces. i.e.. approximately fifteen single-space typewritten lines) (16) hl NO SUBMISSION DATE (15)

I I I On July 14, 1988 at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, with Unit 1 at lOE-7 amp intermediate range and Unit 2 at 100% power, it was determined the Technical Specification that required sampling had not been performed within the required time frame. Technical Specification Table 3.7-S(a) requires that the service water side of the component cooling (CC) water heat exchangers (EIIS-HX) be sampled and analyzed for radioactive contamination every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Due to an error made by the technician performing the analysis, one sample for the "B" and "C" CC heat exchangers was discarded without the proper analysis being performed.

This resulted in the samples being performed approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> apart. Radiation levels of samples prior to and following the missed samples were within specified limits.

Samples of the "B" and "C" heat exchanger service water were immediately obtained and analyzed. The analysis of samples were found to be.within acceptable limits. Personnel were reinstructed in the importance of thorough analysis.

. 980803 S80915040C1e 05000280 pDR AD "'

• PNU s

NRC Form 366 19-831

POW 28-06-01

' N RC Form 366A (9-83)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPAOVEO 0MB NO. 3150--0104 EXPIRES: 8/31/88

\ FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (61 PAGE (3)

YEAR ::::::::::: SEQUENTIAL ::;:::::::: REVISION

NUMBER  :::::::::: NUMBER Surry Power Station, Unit 1 TEXT /If man, space is requinJd, usa additional NRC Form 3156A 's/ (17) 1.0 Description of the Event On July 14, 1988 at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, with Unit 1 at lOE-7 amp intermediate range and Unit 2 at 100% power, it was .determined the Technical Specification that required sampling had not been performed within the required time frame. Technical Specification Table 3.7-5(a) requires that the service water (SW) side of the component cooling (CC) water heat exchangers (EIIS-HX) be sampled.and analyzed for radioactive contamination every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Due to* an error made by the technician performing the analysis, one sample for the "B" and "C" CC heat exchangers was discarded without the proper analysis being performed. This resulted in the samples being performed approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> apart. Radiation l~vels of samples prior to and following the missed samples were within specified limits.

2.0 Safety Consequences and Implications The component ' cooling system is an intermediate cooling system which serves both reactor units. It transfers heat from heat-exchangers containing reactor coolant, other radioactive liquids, and other fluids to the service water system.

Since there was no increase in the circulation water discharge radiation monitor (indication of CC to SW tube integrity) during this event, the health and safety of the public were not affected.

3.0 .Cause The service water contamination analysis procedure consists of three steps: (1) place sample in dete~tor, (2) erase old data/

start new data acquisition, and*(3) perform analysis on new data.

In this event, the technician performing the procedure neglected to perform step 2. Step 3 was therefore performed on old data and proper analysis of the new samples was not obtained.

4.0 .Immediate Corrective Action(s)

Samples of the "B" and "C" heat exchanger service water were immediately obtained and analyzed. The analysis of samples were found to be within acceptable limits.

5.0 Additional Corrective Action(s)

None:

NRC FORM 366A (9-83)

POW 28-06-01 NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150--01u4 EXPIRES: B/31 /88

\ FACILITY NAME (1 I DOCKET NUMBER (21 LER NUMBER (~I PAGE (31 Surry Power Station, Unit 1 0 1s IO IO IO I 21 8 10 s, s - 0 I 21 7 - 0 IO Oj 3 OF O I3 TEXT (If morr, spscs i* required, uSII addftional NRC Form 366A '*I (171 6.0 Action(s) Taken to Prevent Recurrence Personnel were reinstructed in the importance of thorough analysis.

7.0 Similar Events None.

8.0 Manufacturer/Model Number N/A NRC FORM 366A (9-831

'-~

VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P. o. Box 316 Surry, Virginia 23883 August 3, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-035 Document Control Desk Docket :No.: 50-280 016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report_for Surry Unit 1.

REPORT NUMBER 88-027-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours,

~A~

Q ~

David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323