ML18153C621

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LER 91-005-00:on 910413,failure to Sample Svc Water from Component Cooling HX Discovered.Caused by Personnel Error. Radiation Monitor Sys for Svc Water Discharge from Component Cooling HXs Replaced W/Improved sys.W/910510 Ltr
ML18153C621
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/10/1991
From: Kansler M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-275, LER-91-005-01, LER-91-5-1, NUDOCS 9105210287
Download: ML18153C621 (5)
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Virginia Electric and Power Company Surry Power Station P.O.Box315 Surry, Virginia 23883 May 10, 1991 U.S. Nuclear Regulatory Commission Serial No.: 91-275 Document Control Desk Docket Nos.: 50-280 Washington, D. C. 20555 50-281 License Nos.:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Units 1 and 2.

REPORT NUMBER 91-005-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by the Corporate Management Safety Review Committee.

Very truly yours, M. R. ansler Station Manager

  • Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323
  • ) 10521 <)287 91.0510 PDR ADOO< 050002
    ::0 PDR

I' NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: so.a HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR

' REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT .(3150-0104), OFFICE I

OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) I PAGE (3)

Surry Power Station, Unit 1 o Is f o f o f o 12 I 81 o I 1 loF 01 4 TITLE (41 Failure to Sample Service Water From Component Cooling Heat Exchanger Within Technical Specification Required Interval Due to Personnel Error EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY VEAR VEAR ((f SEQUENTIAL NUMBER rt REVISION NUMBER MONTH DAV YEAR Surry, Unit 2 FACILITY NAMES DOCKET NUMBER(S) 0 1s101010,2 18 I 1 ol 4 113 9 1 91 1 olo Is - oj 0 ol 5 1 lo 911 0 ,s,o IO I o, I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR §: (Check one or more of rh* following) (11)

MODE (9) N 20.402(b) 50,73(o)(2Hiv) 73.71(bl 20.405(c) 20.406(0)(1 )(i) 50,36(c)(1) 50.73(o)(2)(v) 73.71(c)

POWER LEVEL (10) 11 I 010 20.405(0)(1 )(ii)

,__ 50.36(c)(2) 50.73(o)(2)(vii)

OTHER (Sp*cify in Absrr*cr bolow tJnd in TfJxt. NRC Form

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20.405(0)(1 )(iii) 50.73(o)(2)(i) 50.73(0) (2) (viii) (A) 366A) 1111111111111:lilllll

..._ 20.405(0)(1 )(iv) 20,406(*1!1 )(v)

..._ 60.73loH2Hii) 50.73(oJ(2)(iii)

LICENSEE CONTACT FOR THIS LER (12)

- 50.73(0) (2) (vi iii (Bl 50.73(o)(21lx)

NAME TELEPHONE NUMBER AREA.CODE M. R. Kansler, Station Manager 810 I 4 31 51 7 1- I 31 l 18 I 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) re* .. *.* .........  :,::,*.*, .*.*,

MANUFAC- REPORTABLE ........

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I I I I I I I 1:-:-:-:, :-:*>****  :-:-: I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY VEAR EXPECTED n YES (If yes, comp/ere EXPECTED SUBMISSION DATE)

ABSTRACT (Limit to 1400 spaces. i.e .. approximstely fifteen single-space typewritten lines) (16) hi NO SUBMISSION DATE 1151 I I I On April 13, 1991, with Unit 1 operating at 100% power and Unit 2 at Cold Shutdown, it was discovered that the Technical Specification

_requirement for sampling the Service Water (SW) discharge from the "C" Component Cooling (CC) Heat Exchanger had not been performed within the specified interval. Technical Specification Table 3.7-5(a) required that the SW effluent

  • from a cc Heat Exchanger be sampled and analyzed for radioactivity at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the effluent radiation monitor was out of service. Consecutive samples were taken 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 33 minutes apart. The -event had no safety consequences since analysis of the late sample detected no radioactivity, indicating that leakage of radioactive liquid into the SW system was not occurring. The event was caused by personnel error.. Following the event, the sampling frequency was increased to twice each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift. An improved radiation monitoring system for the SW discharge from the cc Heat Exchangers has been installed and placed in service.

This report is required by 10CFR50. 73(a)(2)(i)(B) since failure to obtain the required SW sample within the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> maximum sampling interval is a condition not allowed by Technical Specification 3.7.

NRC Form 366 {6-89)

NRC FORM /j6SA U.S. NUCLEAR REGULATORY COMMISSION

(~;89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

Surry Power Station, Unit 1 o Is Io I o I O I 2 18 I o 9 11 _ o I oI 5 _ o Io o 12 oF o14 TEXT (If more spac,, is -,uimd, use *ddltional NRC Form 3QiA's/ (17) 1 .O DESCRIPTION OF THE EVENT On April 13, 1991 at 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, with Unit 1 operating at 100% power and Unit 2 at Cold Shutdown for a scheduled refueling outage, it was discovered that the Technical Specification requirement for sampling the Service Water (SW) [EIIS-BE] discharge from the "C" Component Cooling (CC) Heat Exchanger [EIIS-CC,HX] had not been performed within the specified time interval. Technical Specification Table 3.7-5(a) required that the SW effluent from a CC Heat Exchanger be sampled and analyzed for radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the SW radiation monitor [EIIS-BE,RM] was out of service.

The previous sample for the "C" CC Heat Exchanger had been taken at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> on April 12, 1991. At 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> on ApriL 13, 1991, a non-licensed Turbine Building Operator Trainee noted that the sample which was due at 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> had not yet been taken. A sample was taken at 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />, analyzed, and found to contain no detectable activity.

This report is required by I0CFR50.73(a)(2)(i)(B) since failure to obtain the required SW sample within the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> maximum sampling interval is a condition not allowed by Technical Specification 3.7.

2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS The Component Cooling System is an intermediate cooling system which serves both units. This system transfers heat from heat exchangers containing reactor coolant and other_ radioactive fluids to the Service Water System. Radiation monitors are provided to detect leakage of radioactive fluid from the CC System to the SW System; however, the monitor for the "C" CC Heat Exchanger was out of service prior to the event, requiring that grab samples be collected and analyzed. The SW sample taken at 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />, as well as the previous sample, contained no detectable activity. Since leakage of radioactive fluid into the SW System was not occurring, there were no actual or potential consequences to public health and safety.

3.0 CAUSE OF THE EVENT The event resulted from cognitive errors by the licensed Liquid Waste Operator, who was responsible for ensuring that the SW sampling was performed, and the non-licensed Turbine Building Operator, who was assigned the task of drawing the sample. Both Operators are Virginia Power employees. The Turbine Building Operator was assigned to perform routine Unit 1 and Unit 2 Turbine Building rounds. While performing the Unit 1 portion he interrupted his rounds to investigate NRC Form 366A (6-89)

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NRC FORM'B66A (6:89)

U.S. NUCLEAR REGULATORY COMMISSION APPROVEO 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 60.0 HRS. FORWARD

,, TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1'HE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (61 PAGE 131 YEAR Surry Power Station, Unit 1 TEXT (H _,,. tl/M~ la ,wqund, u.se *dd/r/onal NRC Fann 3511A'a) 1171 a problem in the Unit 2 Turbine Building. The Operator then decided to begin performing Unit 2 rounds, delaying completion of the Unit 1 rounds. This resulted in the "C" CC Heat Exchanger SW sample being taken 33 minutes late, since the drawing of the sample .was part of the Unit 1 rounds. The Liquid Waste Operator had not adequately communicated to the Turbine Building Operator the need to obtain the SW sample within the Technical Specification interval.

4.0 IMMEDIATE CORRECTIVE ACTIONCSl The required SW sample was taken three minutes after it was realized that the sample was late. The sample was analyzed and was found to contain no detectable activity.

5.0 ADDITIONAL CORRECTIVE ACTIONCSl None.

6.0 ACTIONS TO PREVENT RECURRENCE Following the event, samples of SW discharge from the "C" CC Heat Exchanger were taken twice per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift to reduce the probability of a late sample.

The radiation monitor system for the SW discharge from the CC Heat Exchangers has been replaced with an improved system. The new design features a sodium iodide crystal detector mounted in a drywell in each lieat exchanger. This design contains no piping subject to fouling and no pumps to . maintain, and provides an individual detector for each heat exchanger. The system has been placed in service on all four CC Heat Exchangers.

7.0 SIMILAR EVENTS Licensee Event Report (LER) 1-89-034 described an event where a SW sample from a CC Heat Exchanger discharge was taken outside the Technical Specification required interval. The event was caused by ineffective communication between the licensed Liquid Waste Operator and the non-licensed Turbine Building Operator. Corrective action for this event' included revision of the Liquid Waste Operator's log to include a section where the time and date of the last sample and the deadline for the next sample are entered. This corrective action is still in effect but did not prevent the April 13, 1991 event.

NRC Form 366A (6-89)

NRC FORM S66A (6-891 U.S. NUCLEAR REGULATORY COMMISSION APPROVEO 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, ANO TO l'HE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1)

  • DOCKET NUMBER (2) PAGE (3)

LER NUMBER (61 YEAR ,',',',',' SEQUENTIAL ;:;:;:;:::* REVISION

NUMBER  ::::::::;: NUMBER Surry Power Station, Unit 1 o 1s Io Io Io I 21 s I o 911 - o I 01 s - o Io o 14 oF o 14 TEXT (If mom lpllt:e ia n,quired, UM additional NRC Form 366A'a) (17)

LERs 1-88-027 and 1-89-017 described events where SW samples were not properly analyzed. In both of these events, technicians performing the sample analyses failed to perform a step in the analysis procedure. The corrective actions for these events would not have prevented the April 13, 1991 event.

LERs '1-88-045, 1-89-007, 1-89-018, and 1-90-013 also address instances where Technical Specification required sampling was not accomplished within the required time period. These events were due to the following reasons, respectively: (1) equipment failure and misinterpretation of the Technical Specification, (2) an incorrect assumption that equipment would be returned to service within a certain time frame precluding the need to obtain a sample, (3) an incorrect sample time log entry, and (4) unexpected delays encountered in radiological control activities. The corrective actions taken for these events would not have prevented the April 13, 1991 event.

8.0 ADDITIONAL INFORMATION

  • None.

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NRC Form"366A (6-891

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