ML18153B902

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LER 89-027-00:on 890815,containment Gaseous Radiation Monitor Momentarily Increased Above Alarm Setpoint,Resulting in Closure of Containment Instrument Air Compressor Valves. Caused by Increase in Airborne concentration.W/890908 Ltr
ML18153B902
Person / Time
Site: Surry Dominion icon.png
Issue date: 09/08/1989
From: Kansler M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-038, 89-38, LER-89-027, LER-89-27, NUDOCS 8910020276
Download: ML18153B902 (5)
v • d • e


Text

,.

e e VIRGINIA ELECTRIC ANO POWER COMPANY Surry POMr Station P. 0. Bo* 315 Surry, Virginia 23883 September 8, 1989 U.S. Nuclear Regulatory Commission Serial No.: 89-038 Document Control Desk Docket Nos.: 50-280 Washington, D.C. 20555 50-281 License Nos: DPR-32 DPR-37 Gentlemen:

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 89-027-00 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,

//~

Station Manager Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 8910020276 890908 PDR ADOCK 05000280 S PDC

POW 28-06-01 e

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIONI. APPROVED OMB NO. 31 50-0104 ,

(6'89) _ '

I' _., , EXPIRES: 4/30/92 STIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) gg'Ji:rf/~ 1~~~<;,.~~~~~T~~~tEENo~i;11A;!le\~~~/~:c~'6~

AND REPORTS MANAGEMENT BRANCH IP-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT AND BUDGET,.WASHINGTON, DC 20503.

FACILITY NAME (11 DOCKET NUMBER (2) PAGE (31 Surry Power Station,. Unit 1

!01s1010101 I I 1 loF O 14 TITLE (4) Unplanned ~ng1neerea ~arety r*eatures Component Actuation, G~osure of Containment Isolation Valve Due to Containment Gaseous Radiation Monitor Alarm EVENT DATE (51 LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR ttt SE~~~~~~AL t( ~~t~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI oIs 1I s s 9 s 19 - o 12 1 1 - o Io oI 9 o 1s s 19 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR §: (Chock on* or more of rh* following) (11 l MODE (9)

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LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager 81 0 14 31 5 17 I -1 3 1 l 1 8 I 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC- MANUFAC*

CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TURER TURER I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION I YES /If v**, compt*rs EXPECTED SUBM/SS/ON DATE/

DATE 1151 I I I ABSTRACT (Limit to 1400 spactJs, i.e., approxim*tt1ly fift11n singltJ*SPIJCtJ typt1written lines} (16)

On August 15, 1989 at 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br />, with Unit 1 at 100% power, the containment gaseous radiation monitor momentarily increased above the alarm setpoint. The alarm resulted in the closure of the.

containment instrument air (IA) compressor's normal suction valves from containment and the opening of the alternate suction valve outside containment. The containment valves also close upon an Engineered .Safety Features (ESF) signal. This event is being reported as an unplanned ESF component actuation. A four hour non-emergency report was made to the Nuclear .Regulatory Commission per 10CFR50.72. The alarm was reset, and the IA compressor suction valves were realigned to their normal position. The basis for the alert and alarm setpoints of the containment particulate and gaseous monitor are being evaluated.

NRC Form 366 (6-89)

e NRC FORM 366A U.S. NUCLEAR. REGULATORY COMMISSION *

. (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CON TIN UATIO N 0

FJn':i~.r:-rc:c:iNu~gE~E~~~:E~:i~~~/ 5o~~~R's:

COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS

~tw~1 g AND REPORTS MANAGEMENT BRANCH (P-5301, 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 (11 DOCKET NUMBER (2) PAGE (31 LER NUMBER (61 Surry Power Station, Unit 1 o 1s Io Io Io I 2 18 *1 o 8 19 - OI 217 - o 10 o 12 OF o 14 TEXT (ff more 11pace is n,quimd, U/ll!J *ddltioMJ NRC Form 36'&4 'aJ (17) 1.0 Description of the Event

  • On August 15, 1989 at 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br />, with Unit 1 at 100%

power, the containment gaseous radiation monitor (RI-RMS-160) (EIIS-IL, MON) momentarily increased above the alarm setpoint. The radiat"ion monitor was in the alert condition at the time of the event.

Normal fluctuations in monitor indications resulted in a momentary increase above the alarm setpoint for the alert condition.

The alarm resulted in the closure of the containment instrument air (IA) compressor's (EIIS-LD,CMP) normal suction valves (EIIS-ISV) (TV-IA-101A and B) from containment and the opening of the alternate suction valve outside containment (AOV-IA-103). The IA compressor normal suction valves are also designed to close upon the initiation of a high Consequence Limiting Safeguards (CLS) signal. However, no actual high CLS signal was present. The event is being reported as an unplanned Engineered Safety Features (ESF) (EIIS-JE) component actuation. A four hour non-emergency report was made to the Nuclear Regulatory Commisston per 10CFR50.72.

2.0 Safety Consequences and Implications The containment IA compressors are located outside containment. Their normal air supply is provided from containment via two series containment isolation trip valves. These valves automatically shut on a high CLS signal or when a high containment radiation alarm is received. The alternate suction valve opens when either trip valve is closed, allowing the compressor to receive air from the safeguards area outside containment. This ensures that, following an accident inside containment, a leak that develops in the IA system outside of containment w9uld not result in a radiation release to atmosphere.

During this event, there was no significant increase in containment radiation, and the IA valves functioned as designed to isolate containment. The containment IA system remained operable with its air supply being provided through the alternate suction. Therefore, -

the health and safety of the public were not affected.

NRC Form 366A (6-891

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-891 ,

  • APPROVED 0MB NO. 3150-0104

.. EXPIRES: 4/30/92 ESTIMATED BURDEN PEA RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) 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)

VEAR  :::::::::: SEQUENTIAL *:*:*:*:*:* REVISION

NUMBER  :,:,:*:*:* NUMBER Surry Power Station, Unit 1
  • o 1s I 0*1 o Io I 218 I* o 819 __ 01 217 _ o 1o o 13 OF o 14 TEXT (If more.,,..,, i6 /'9(/Uimd, U6tJ additional NRC Fann 315S4'a) (17) 3.0 Cause The containment gaseous radiation monitor alarm and alert setpoints are maintained slightly above ambient levels to promptly alert the operators of an increase in containment airborne concentration. New.alarm and alert setpoints had* been established on June 30, 1989,

_just prior to a unit startup, based on containment background levels at the time. Slow increaseis in containment gaseous activity, which is expected due to small Reactor Coolant System (RCS) identified leakage during operations, resulted in the radiation monitor indication exceeding the alert setpoint on August 14.

Normal fluctuations in monitor indications resulted in a momentary increase above the alarm setpoint from the alert condition resulting in the valve repositionings discussed herein. Health Physics personnel had been

~ notified of the alert condition that occurred on the previous day and were in the process of calculating new alert and alarm setpoints when the alarm occurred.

No radioactive release occurred.

  • 4.0 Immediate Correc~ive Action(s)

The containment gaseous radiation monitor indication was verified to decrease to belbw the alarm setpbiht.

The alarm was reset, and the IA compressor suction valves were realigned to their normal position.

5.0 Additional Corrective Action(s)

The radiation monitor readings were -validated by Health Physics pe!sonnel based on an isotopic analysis of a containment sample. New alarm and alert setpoints were calcuiated and entered into the radiation monitor.

6.0 Action(s) Taken to Prevent Recurrence The basis for the alert and alarm setpoints of the containment particulate and gaseous monitor are being evaluated. Appropriate actions will be taken upon completion of this evaluation.

NAC Form 366A 16-891

l NRC FORM 366A (6-891 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION e APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92

.ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD 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 (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (61 PAGE 13}

Surry Power Station, Unit 1 0 I5 IO IO I O I 218 I O 8 19 - 0 I 21 7 - 0 IO O 14 OF O 14 TEXT (H more spaCtJ i& f9qUirw/, U/JO lldditioMI NRC Form 3156A's/ 117) 7.0 Similar Events None.

8.0 Manufacturer/Model Number(s)

N/A NRC Form 366A 16-89)

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