ML18153C417

LER 90-013-00:on 900928,licensee Failed to Obtain Wgdt Sample within Tech Spec Sampling interval.W/901026 Ltr

ML18153C417
Person / Time
Site:	Surry
Issue date:	10/26/1990
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-664, LER-90-013, LER-90-13, NUDOCS 9011070041
Download: ML18153C417 (5)

Text

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Virginia . Electric and

• Power Company Surry Power Station

• P. 0. Box 315 Surry, Virginia: 23883

• October 26,

• 1990 U. S. Nuclear Regulatory Commission Serial No.: 90-664 Document Control Desk Docket No.: 50-280 Washington, D. C. 20555 ~0-281

. License Nos.": DPR-32 Gentlemen: DPR~37 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 90-013-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Corporate Nuclear Safety.

Very truly yours,

. Station Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia

• 30323

. ~ -* i;""

t .t. (,f 9011070041 901026 PDR ADOCK 05000280 S PNU

NACFOAM386 CS-891 '

e U.S. NUCLEAR REGULATORY COMMISSION

e. APPAOVEO 0MB NO. 3160-0104 EXPIRES: 4130192 ESTIMATED .BURDEN PEA RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 60.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI . COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-630) .. U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 1315CMl104l, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503, FACILITY NAME C1l DOCKET NUMSEA 121 I f'AUl:l:11 Surry Power Station, Units 1 and 2 01s1010101 I I 1 loF 014 TITLE 141 Failure to Obtain WGDT Sample Within Technical Specific~tion Sampling Interval MONTH EVENT DATE CIII DAY YEAR YEAR LEA NUMBER Ill ft SE~~~:r~AL Jt =~= MONTH IIEPOIIT DATE 171 DAY YEAR OT~EII FACILITIEI INVOL',IED CII FACILITY NAMES DOCKET NUMBEAISl oI9 21 a 9 o 9 lo - o I 1 I3 - oIo 1 Io 2 I6 9 lo 01s1010101 I I THII IIEl'ORT II IUIIMITTED PUAIUANT TO THE llkOUIIIEMENTI OF 10 CFA §: (Chd - or mor9 of 1M followinJ/ C11 l OPERATING N

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- I0.711all2lMIIIIAl 366A)

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LICENSEE CONTACT FOIi THIS LEA C121 I0.711ell21111YICII I0.731elC2ll*l NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager COMPLETE ONE LINE FOR EACH COWONENT FAILURE DEICIIIIED IN THIS IIEl'ORT 1131 MANUFAC* MANUFAC-CAUSE SYSTEM COMPONENT TURER

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_On September 28, 1990, with Unit 1 at 57% power and Unit 2 at 100% power, the Technical Specification sampling interval_ for the "A" Waste Gas Decay _Tank was exceeded. This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B) since it is a condition not allowed by _Technical Specifications. The everit was caused by unexpected delays encountered in radiological control. activities. A sample was taken, analyzed, *ancl verified to be within acceptable limits. Modified hydrogen and oxygen analyzers are expected to be in service by December 31, 1990, eliminating the requirement. for . routine grab ~ampling.

NRC F<<ffl 3111 C&-1191

NRC FORM 366A 16-891 '

LICENSEE EVENT REPORT (LER) e U.S. NUCLEAR REGULATORY COMMISSION e APPROVEO 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 Surry Power Station, Units 1 and 2 0 15 IO IO IO I 21 8 I O *910 - 0 11 I 3 - 010 01 2 OF O I4 TEXT (If mtn ,,,_ * ,.,..,_,, - MltlJtioMI NRC Fann .ifiM'*J {17i 1 . 0 DESCRiPTION OF THE. EVENT On September 28, 1990, at 1355 ~ours, with Unit l at 57%

power and Unit 2 at 100% power,* the Technical Specification sampling interval for the "A" Waste Gas Decay Tank (EIIS-TK) was exceeded. Technical Specification 3. 7 .E reqmres that the Waste Gas Holdup System (EIIS-WE) 'hydrogen and oxygen monitors (EIIS-MON) be . <>perable. If one hydrogen and one oxygen monitor are. not operable, continued system. operation is permitted provided that grab samples are collected at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> : and analyzed within the following four hours.

• The hydrogen and oxygen monitors are inoperable and grab samples are taken to satisfy the Technical Specification requirement. A grab. sample was taken at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> on September 27, 1990, but by . 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> on September 28, 1990 another* sample had not been taken. The sample was not drawn until 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br />, resulting m the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> maximum sampling interval being exceeded by 15 minutes.

This report is required by 10 CFR 50.73(a)(2)(i)(B), smce failure to obtain the required grab sample within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> maximum sampling interval 1s a condition not allowed by Technical Specification 3. 7 .E.

2. 0 SAFETY CONSEQUENCES AND IMPLICATIONS

• Hydrogen and oxygen concentrations in the Waste Gas Holdup System are monitored so that an explosive gas mixture can be prevented. Hydrogen and oxygen analyses of the sample drawn at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> on September 28, 1990, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 15 minutes after the previous sample, were within acceptable limits. Therefore, the health and safety of the public were not affected.

NRC Fenn 366A 16-89)

NRC FORM 366A

(~9) e U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)

APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-630). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TC 1'HE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE QF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2)

LER NUMBER (6) PAGE (3)

YEAR  :::::::::: SEQUENTIAL ::::::::::* REVISION

NUMBER  :::::::::: NUMBER Surry Power Station, Units 1 and 2 01s101010121s10 910 -01113 -010 013 OFO 14 3.0 CAUSE The sample was not taken on time due to unexpect(!d delays encountered in radiological control activities. The operator assigned to take the sample left the control room area at 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br />. The 30 minutes alloted to the sampling process is more than adequate undet normal circumstances, since the drawing of the sample requires only about five minutes. The operator proceeded to the Health Physics area to obtain the required dosimetry and protective clothing; howev~r, the equipment used to issue Digital Al;uming Dosimeters was temporarily out of service, delaying the issuance of dosimetry. The operator obtained his dosimetry at 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br />, then checked the posted dress out requirements, which indicated that the sampling area was a contaminated area. The operator dressed out accordingly and proceeded. to the sampling area. Upon arrival, the operator became aware that the sample area status had been changed to a hot particle area, reqmnng additional protective clothing.

The change m sample area status to a hot particle area had occurred at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> that day, and the postings m the dress out area had not yet been updated. These postings are normally updated once per day. The operator contacted the control room at 1346 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12153e-4 months <br /> to inform control room operators of the situation, then returned to the dress out area m order to change protective clothing prior to drawing a sample. By the time the operator donned the required protective clothing and completed the sampling process, the sampling deadline had been missed by 15 minutes.

4.0 IMMEDIATE CORRECTIVE ACTION(S)

A sample of the "A" waste gas decay tank was obtained at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> on September 28, 1990.

NRC Form 366A C~9)

NRC FOFIM 386A IIHl&'i '

e LICENSEE EVENT REPORT (LER)

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 REQUEST: 60.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1"HE PAPERWORK REDUCTION PROJECT 13150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 ,AOE 131 Surry Power Station, Units 1 and 2 0 I5 I O I O I O I 2 I 81 0 . 91 0 - 0 11 I 3 - 01 0 01 4 OF O I 4 TEXT ft/,,.,,,.~ la n,qulred, - <<klltJoMI NRC Form ~-.J 1111 5.0 ADDITIONAL CORRECTIVE ACTION<S}

Newly modified in-line . hydrogen, *and oxygen mon.itors are expected to be in service by December 31, 1990. When these monitors are m service, regular grab sampling will no longer be required.

6. 0

• ACTIONS TO PREVENT RECURRENCE The corrective action described above 1s considered adequate to prevent recurrence.

7 *0 SIMILAR EVENTS LER Sl-88-045 LER Sl-89-018

8. 0 MANUFACTURER/MODEL NUMBER N/A NRC F - 366A IIM19)