ML17279B178

LER 87-032-00:on 870602,radiation Monitor REM-21WL-3541 Sample Chamber Instead of REM-21WS-354 Drained for Disconnection Leaving Monitor Inoperable.Caused by Personnel Error.Procedure HPP-495 prepared.W/870701 Ltr

ML17279B178
Person / Time
Site:	Harris
Issue date:	07/01/1987
From:	Schwabenbauer, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870455-(O), LER-87-032, LER-87-32, NUDOCS 8707090410
Download: ML17279B178 (7)

Text

.~ULAl INFORNATION DIST UTIOI YSTEN (RIDS)

ACCESSION NBR: 8707090410 DOC. DATE: 87/07/01 NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Power Plant> Unit 1> Carolina 05000400 AUTH. N*NE AUTHOR AFFILIATION SCHMABENHAUER> Carolina Power 8c Light Co.

WATSON> R. A. Carolina Power 8c Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-032-00: on 870602> attempts to refill sample chamber restore sample Plow to radiation monitor resulted in leaving monitor inoperable. Caused bg personnel error.

radiation monitor setpoints revised. W/870701 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR Q ENCL Q SIZE:

TITLE: 50. 73 Licensee Event Report (LER>> Incident Rpt> etc.

NOTES: Application for peTmit renewal filed. 05000400 RECIPIENT COPIES REC IP IENT COP IEB ID CODE/MANE LTTR ENCL ID CODE/NANE LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEY> B 1 INTERNAL: ACRS NICHELSON 1 1 ACRB NOELLER 2 2 AEOD/DOA 1 AEOD/DSP/ROAH 2 2 AEOD/DSP/TPAB 1 1 DEDRO 1 NRR/DEBT/ADE 0 NRR/DEST/ADS 1 0 NRR/DEBT/CEH 1 1 NRR/DEBT/ELH 1 1

. NRR/DEBT/ICSH 1 1 NRR/DEST/NEB 1 1 NRR/DEBT/NTH 1 1 NRR/DEBT/PSB 1 NRR/DEST/RSH 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFH 1 NRR/DLPG/G*H 1 NRR/DOEA/EAH 1 1 NRR/DREP/R*B 1 1 NRR/DREP/RPH 2 2 NRR/PNAS/ILRB 1 1 NRR/PNAS/PTSB 1 1 R FNL= 02 1 1 RES DEPY GI 1 1 ES TELFORD> J 1 1 RES/DE/EIH 1 1 RGN2 FILE 01 1 1 EXTERNAL: EQ8(G GROH> N 5 5 H ST LOBBY NARD 1 1 LPDR 1 1 NRC PDR 1 NSIC HARRIS> J 1 1 NBIC NAYS> Q '1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 42

NAC Form 388 U.S. NUCLEAR REOULATOAY COMMISSION (8.831 AI PAOVEO OMB NO. 3(504(04 EXPIRES: 8/31/BS LICENSEE EVENT REPORT (LER)

FACILITY NAME (11 DOCKET NUMBER (2) PA E 3 SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 00 1 OFO 4 TITLE (4)

RADIATION MONITOR REM-21WL-3541 INOPERABLE EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH OAY YEAR YEAR xaam SEQUENTIAL NUMBER N NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBERIS) 0 5 0 0 0 0 60 28 87 0 3 2 00 701 87 0 5 0 0 0 THls REPDRT Is sUBMITTED PURsUANT To THE REQUIREMENTs oF 10 cFA (): fcheck one or more ol the foiiovflnpl (11)

OPERATINO MODE (8) 20.402(B) 20.405(c) 50.73(ol(2)(lv) 73.71(B)

POWER 20.405( ~ ) II I(i) 50M(c)(() 50.73(e)(2((v) 73.71(c)

LEVEL 1 p p 20.405 (e) (1) (il) 50.38(cl(2) 50.73(e) (2((vill OTHER ISpeclly In Ahttrect Below encl In Text, IIRC Form 20.405( ~ l(1((ill) X 50.73(ol(2)(ll 50.73(o) (2) (vill)(Al SBBAI 20AOS (e ) (I l(lv) 50.73(o) (2) (8) 50.73(o) (2)(vill)(B) 20A05(ol(1) (v) 50.73(ol(2) (ill) 50.73( ~ )(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE R. SCHWABENBAUER REGULATORY COMPLIANCE 9 1 6 2-COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE MANUFAC.

r" '". 'N ' ".

CAUSE SYSTEM COMPONENT MANUFAC. CAUSE SYSTEM COMPONENT EPORTABLE 'O NPROS TUAER

'O TURER NPADS

...'..h.h. C

@RP m>

54M!8 h

~N4;m~

SUPPLEMENTAL AEPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YES Ilfyet, complete EXPECTED SUBMISSIDII DATEI NO ABsTAAcT ILimlt to f400 tpecet, I e., epproxlmeNly fifteen tlnpie opere typewritten linnl (18)

ABSTRACT The plant was operating in Mode 1 at 100 percent reactor power on June 2, 1987 'he Waste Monitor Tank Liquid Radiation Monitor (REM-21WL-3541) was mistakenly removed from service and the sample chamber was drained on June 1, 1987 at approximately 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />. Attempts to refill the sample chamber and restore sample flow to the monitor resulted in leaving the monitor inoperable and with incorrect information on the status of the monitor displayed on the Radiation Monitoring System computer. When the error was discovered at approximately 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> on June 2, 1987, a liquid release was being made through this monitor. When the sample flow started, a high radiation alarm terminated the release. Chemistry was requested to collect samples which, when analyzed, agreed with the pre-release sample activity. The unmonitored release was a violation of Technical Specification 3.3.3.10.b, Table 3.3-12, Action 35

'o safety consequences resulted from this event. The release was immediately terminated by a high radiation alarm. Chemistry samples and analyses showed that no limits were exceeded. The high radiation alarm was due to either a noise spike resulting from the pump startup or to a concentrating effect of the activity in the entrance to the previously stagnant sample lines.

8707090410 870701 PDR ADOCK 05000400 S PDR NRC Form 388 l4 831

NRC form 388A U.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3(50-0104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) PACE (3)

SHEARON HARRIS PLANT YEAR N

'm. SEOUENTIAL NUMSER REVISION P%'4 NUMBER UNIT 1 o s o o o4 00 87 0 3 2 0 0 p20Fp TEXT /8'moro <<>>co /8 r/vlvtor/, I/88 ////OI>>/ kRC Forrrr 38549/ (17)

DESCRIPTION Plant condition during the following event was Mode 1 at 100 percent reactor power. On June 1, 1987 at approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, the Radiation Control (RC) Foreman requested an RC Tech. (Technician no. 1) to go to Radiation Monitor REM-21WS-3542 (Secondary Waste Tank), drain the sample chamber, and examine the components so that Technical Support personnel could determine replacement part numbers. Monitor REM-21WS-3542 was inoperable at the time due to a high temperature problem in the sample lines.

Technician no. 1 proceeded to Monitor REM-21WL-3541 (Waste Monitor Tank),

thinking that it was REM-21WS-3542. Both monitors are located in the Tank Room at the 236'levation and have app'ropriate labelling. Technician no. 1 proceeded to isolate REM-21WL-3541 and drain the sample chamber for disconnection. The monitor actuated a loss-of-sample flow alarm at 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />. Since there was no release in progress at the time, the technician (Technician no. 2) at a Radiation Monitoring System control console (RM-ll console) in the RWP office, acknowledged the alarm without taking any immediate action to try and restore flow.

Technician no. 1 suddenly realized that he was at the wrong monitor. He reconnected all fittings and notified Technician no. 2 that he had drained the wrong monitor, but had reconnected and unisolated the monitor. Technician no.

2 requested sample flow to the monitor via RM-ll at 1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br />. Several unsuccessful attempts were made to reestablish sample flow in REM-21WL-3541.

Technician no. 1 called the Radiation Control (RC) Foreman and asked how to reestablish flow in a liquid monitor. The RC Foreman gave specific instructions over the phone on how to use a portable control console (RM-23P) locally at the monitor skid to establish flow. Part of those instructions included using the RM-23P to put a substitute value of 001 into the monitor's microprocessor (into Monitor Item 001), turning the skid flow-pump to HAND control, and operating the purge one or more times until flow is established.

Technician no. 1 decided to put the value of 001 into Monitor Item 001 via the RM-ll before proceeding to check out an RM-23P and going to the monitor.

However, when he entered the value of 001 int'o Monitor Item 001, he thought that flow had started since the RM-11 indicated there was flow and showed a value for the flow-rate. He did not know that a value of 001 in Monitor Item 001 was also designed to produce other substitute indications.

Technician no. 1 requested a purge several times at the RM-ll to ensure that the monitor did not lose flow, decided that everything was working fine and ended his shift, forgetting to remove the value of 001 from Monitor Item 001. The monitor was not checked locally to confirm proper status.

During the next shift, a liquid release (0 870996) was requested that would be monitored by REM-21WL-3541. The request was processed and the release was started at 0401 hours0.00464 days <br />0.111 hours <br />6.630291e-4 weeks <br />1.525805e-4 months <br /> on June 2, 1987.

NRC FORM 388A *U.S.GPO:1988+.824 538/455 (983)

~ ~

NRC Form 358A U.S. NUCLEAR fIEGULATORYCOMMISSION (84)3)

LICENSEE E NT REPORT (LER) TEXT CO TINUAT N APPROVEO OMB NO. 3150-0)04 EXPIRES: 8/31/88 FACILITYNAME (1) OOCKET NUMBER (2) LER NUMBER (5) PAGE (3)

SEOUEN'rlAL W& REVISION SHEARON HARRIS PLANT YEAR NUMBER ':oB NUMBER UNIT 1 0 5 0 0 0 4 P P 8 7 0 2 0 0 030F0 TEXT /I/moro SF<<co lr /BEUIEI/ Uoo aAWonel HRC Form 3884 3) nil At approximately 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> on June 2,'987, while making routine observations, an RC engineer observed that the trend display on that monitor did not look normal. Suspecting that the data base might not be correct, he asked whether or not a release was being made, and checked to see if there was a substitute value for the sample flow. The value of 001 was found to be present in Monitor Item 001.

When the value of 001 was removed at 0626 hours0.00725 days <br />0.174 hours <br />0.00104 weeks <br />2.38193e-4 months <br />, the monitor actuated a loss of sample flow alarm. When the flow was initiated, a high radiation alarm was received at 0627 hours0.00726 days <br />0.174 hours <br />0.00104 weeks <br />2.385735e-4 months <br />, and the release was automatically terminated.

RC requested that Chemistry (E&C) personnel collect a sample from the tank being discharged. The results of the sample agreed with the pre-release sample.

Since the sample flow pump was not running, the monitor was inoperable and a release was made from 0401 to 0627 hours0.00726 days <br />0.174 hours <br />0.00104 weeks <br />2.385735e-4 months <br /> on June 2, 1987 that was unmonitored and in violation of Technical Specification 3.3.3.10.b, Table 3.3-12, Action 35.

CAUSE The RC Technician failed to follow specific instructions from his foreman for establishing liquid sample flow. Since there was no formal procedure, he felt that using the RM-ll was an acceptable approach. Had he used the RM-23P locally at the monitor, he would have been able to tell that the pump was not actually running.

He also failed to follow procedure AP-521, Control of RMS Data Sheet Library, in that he did not restore and document the temporary data base change (Monitor Item 001) to its Data Sheet Library value.

ANALYSIS As stated above, this event violated Technical Specification 3.3.3.10.b, Table 3.3-12, Action 35. This specification requires that with the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, at least two independent samples must be analyzed, and at least two technically qualified members of the facility staff must independently verify the release rate calculations and discharge line valving. Because the monitor was assumed to be operable, these actions were not taken.

NRC FORM SBBA <<U.S.GPO:1088.0-824.538/455 B)43)

NRC Form 388A U.S. NUCLEAR REOULATORY COMMISSION (983)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATI N APPROVED OMB NO. 3150M) 04 EXPIRES: 8/31/88 FACILITY NAME ll) DOCKET NUMBER (2) LER NUMBER (6) PACE (3)

SHEARON HARRIS PLANT YEAR .~

/I.: SEQVENTIAL NVMEE'R oC'EYISION

':?8 NVM ER UNIT 1 87 03

%%dnrr 0 5 o o o 4 0 0 2 0 0 04 oF 0 4 TEXT (0'/88/8 <<ocr /r/8//Io ~ / Irro //8/orM/HRC 36'El ((7)

ANALYSIS (continued)

No safety consequences resulted from this event. The release was immediately terminated by a high radiation alarm when the sample pump was started.

Chemistry personnel collected a sample, both at the monitor skid and from the tank being discharged. The analysis agreed with the pre"release sample. The high radiation alarm was due to either a noise spike resulting from the pump startup (which is not uncommon) or to a concentrating effect of the activity in the entrance to the previously stagnant sample lines.

This event is reportable under 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications 3.3.3.10.b, Table 3.3"12, Action 35 ACTIONS 'ORRECTIVE

1) The RC Technicians assigned to the RMS have been issued specific direction on following procedural requirements.

2) HPP-498, Radiation Monitor Setpoints for Effluent Releases, has been revised to require the RC Technician to verify the data base prior to Radiation Control signing off on a Release Permit.

3) A new procedure HPP-495, Liquid Monitor Sample Chamber Replacement, is being prepared to give specific steps to follow for restoring sample flow to a liquid monitor after the chamber and sample lines have been drained.

NRC'FORM SEEA *U.S.GP():(988-0-824 538/855 (9E)3)

~ 0

~Q Carolina Power 6 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JUL 01 3987 File Number'SHF/10-13510C Letter Number'HO-870455 (0)

U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-032-00 Gentlemen:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a .written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.

Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc.'Dr. J. Nelson Grace (NRC RII)

Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

MEM/HO-8704550/PAGE 1/Osl