ML17223A790

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LER 89-009-01:on 891025,radiation Monitor RM 8262 Inlet Valve (2-AC-82) Found Closed.Caused by Personnel Error. Isolation Valve Opened,Sample Flow Restored & Radiation Monitor Restored to Operable status.W/900402 Ltr
ML17223A790
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/02/1990
From: Deslandes K, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-009-01, LER-89-9-1, MP-90-322, NUDOCS 9004160214
Download: ML17223A790 (5)
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Text

ACCELERATED STRJBUTION DEMON~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9004160214 DOC. DATE: 90/04/02 NOTARIZED: NO DOCKET N FACIL:50-336 Millstone Nuclear Power Station, Unit 2, Northeast Nu 05000336 AUTH. NAME AUTHOR AFFILIATION DESLANDES,K.D. Northeast Nuclear Energy Co. (subs. of Northeast Utilities)

SCACE,S.E. Northeast Nuclear Energy Co. (subs. of Northeast Utilities)

SCACE,S.E. Northeast Utilities j RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-009-01:on 891025,Radiation Monitor RM 8262 inlet valve (2-AC-82) found closed.

W/9 DISTRIBUTION CODE'E22T COPIES RECEIVED'LTR TITLE: 50.73/50.9 Licensee Event Report (LER), gIncident ENCL J SIZE:

Rpt, etc.

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-4 LA 1 1 PD1-4 PD 1 1 VISSING,G 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DET/ESGB 8D 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 /~SR/ PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 G FILE 02 1 1 RES/DSIR/EIB 1 1 RGN1 FILE 01 1 1 EXTERNAL EG&G STUART E V A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR .1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1

~S>3< P)

/i70 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE.DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 37 ENCL 37

snw aaAsV lmurras The connecticut Light And Power company General Offices Selden Street. Berlin Connecticut Western Massachusetts Electric Company P.O.BOX 270 Hotyoke Water Power Company Northeast Utilities Service Company HARTFORD. CONNECTICUT 06414-0270 Northeast Nuclear Energy Company (203)665-5000 April 2, 1990 MP-90-322 Re: 10CFR50.73(a) (2) (i)

U.S. Nuclear Regulatory Commission Document Control Desk

'tiI'ashington, D.C. 20555

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336 Licensee Event Report 89-009-01 Gentlemen:

This letter forwards Licensee Event Report 89-009-01 required to be submitted pursuant to paragraph 50.73(a) (2) (i). This update report is submitted to reflect a change in the description and analysis of event.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY j

/cA'1 c Step n E. cace Director, Millstone Station SES/KDD:Ijs

Attachment:

LER 89-009-01 cc: T. T. Martin, Region I Administrator W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 and 3 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2

~ ~pd'Pf 9004160214 900402 ~~r PDR ADOCK 0500033r' PDC t/

hiRC Form 366 S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 315~104 (6-89) EXPIRES: 4/30/92 Estimated burden per response to comply with this Information collection request: 50.0 hrs. Forward comments regarding burden estimate to the Records LICENSEE EVENT REPORT (LER) 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.

FACILITYNAME (1) DOCKET NUMBER (2) pa rnl Millstone induc)ear Power Station Unit 2 0 5 0 0 03 3 6 1OF TITLE [4)

Radiation Monitor RM 8262 In)et Va)ve (2-AC-S2) Found Closed EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONT DAY YEAR YEAR SGllCNllAL ';:".a'4JMSDt MONT DAY YEAR FACILITYNAMES 0 5 0 0 0 1025 8 9 8 9 0 0 9 0 I 04 029 0 0 5 0 0 0 OPERATING THIS REPORT IS BEING SUBMiTTED PURsUANT To THE REDUIREMENTs QF 10 cFR tj; (cneck one or more ot the following) (11)

MODE (g) 73,7)(b) 20.402(b) 20. 402(c) 50. 73(a) (2) (iv)

POWER 20.405(a)(1)(I) 50,36(c)(1) 50,73(a)(2)(v) 73.71(c)

LEYEL p p p 20.405(a) (1) (il) 50.36(c) (2) 50.73.(a)(2)(vll) OTHFR (Specify in Abstract below and in 20.405(a) (1) (ill) 50.73(a)(2) (I) 50. 73 (a) (2) (vill)(A) Text. NRC Form 366A) 20.405(a) (1) (lv) 50,73(a) (2) (II) 50. 73(a) (2) (vill)(B) 20.405(a)(1) (lv) 50.73(a) (2) (III) 50.73(a)(2)(x)

LICENScE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA COD Keith D. Des)andes, Engineer, Ext. 4421 2 0 3 4 4 7 1 7 9 1 COMPLETE ON= LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUcAC- <'ci~~~i'"'<"4~'.'";i CAUSE SYSTE MANUFAC-CAUSE SYSTE COMPONcNT TURER COMPONENT TURER SUPPLEMcNTAL REPORT EXPECTED (14) MONT DAY YEAR EXPECTED SUBMISSION DATE (15)

YES (lf yes. complete EXPECTED SUBMISSiON DATE) )( NO ABsTRAGT (Limit to 1400 spaces, l.e., approximately fifteen single-space typewritten lines) (16)

On October 25, 1989, at 1849 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.035445e-4 months <br /> with the plant in cold shutdown mode 5, 0~/o power, it tvas determined that Containment Purge was in operation Nithout an operable radiation monitor capable of isolating the purge on a high radiation sirnal. The sample inlet isolation valve (2-AC-82) for the Facility 2 radiation monitor RM8262 was found closed.

At the time of occurrence the Facility 1 emergency power source (diesel generator) tvas taken out of sertice on October 23, 1989, at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br />. This rendered the Facility 1 radiation monitor RM8123 inoperable, because it was without an emergency power source for its roots blower. Although, emercency power was not available, the radiation monitor remained in sermce. Radiation monitor RM8123 was taken out of service October 23, 1989, at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br /> for maintenance and returned to service October 24, 1989, at 0137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br />.

The radiation monitor was taken out of service again for maintenance on October 24, 1989, at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> and returned to service October 25, 1989, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. During both maintenance activities the Containment Purge was isolated.

Subsequent review showed radiation monitor RM8262 was taken out of service on October 21, 1989, for calibration under procedure SP 2404AL. Restoration from the procedure failed to open sample inlet isolation valve 2-AC-82.

Therefore, no operab)e Containment Atmosphere Particle/Gaseous radiation monitor was available for 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />. During this period of time, Containment Purge was in service for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and isolated for 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />.

Technical Specification Limiting Condition for Operation 3.3.3.1 titled "Radiation Monitoring," and 3.3.2.1 titled "Engineered Safety Feature Actuation System Instrumentation" were not entered. Limiting condition for Operation 3.3.3.1 requires a grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the u'se of a constant air monitor.

Limiting Condition for Operation 3.3.2.1 requires the Containment Purge Valves to be maintained in the closed position.

It should be noted that Health Physics conducted routine outage grab samples of Containment atmosphere with no unusual results during the time the sample inlet isolation valve 2-AC-82 was closed. Also an area radiation monitor is located in Containment on the refuel bridge which continuously monitors the Containment area.

The sample inlet isolation valve 2-AC-82 was opened and radiation monitor RM8262 was declared operable.

NRC Form 366 (6-86)

NRC Form 366A U.S. NUCLEAR REGULATORY COMh4SSION APPROVED OMB NO. 3150-0104 (6-6g) EXPIRES: 4/30/92 EStimated burden Per reSPOnSe tO COmPIy With 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 1o the Paperwork Reduction Project (3150&104). Office of Management and Budget. Washington. DC 20503.

FACII.ITY NAME (1) DOCKET NUMBER (2) LER NUMBER f61 PAGc (3)

...,,... 6(t3/6NIIAL i,, )tens()

YEAR Millstone nuclear Power Station Unit 2 0 5 0 0 0 3 3 6 8 9 0 0 9 0 1 0 2 OF 0 3 TEXT (lf more space is required. uSe additional NRC Form 366A's) (17)

On October 25, 1989, at 1S49 hours with the plant in cold shutdown mode 5, 0'ower, it was determined that Containment Purge was in operation t(ithout an operable radiatioh monitor capable of isolating the purge on a high radiation signal. The sample inlet isolation valve (2-AC-82) for the Facility 2 radiation monitor RMS262 was found closed.

At the time of occurrence the Facility 1 emergency potver source (diesel generator) was taken out of service on October 23, 1989, at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br />. This rendered the Facilit> 1 radiation monitor Riv18123 inoperable, because it was without. an emergency power source for its roots blower.

Although, emergency potter was not available, the radiation monitor remained in service. Radiation monitor RMS123 was taken out ol service October 23, 1989, at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br /> for maintenance and returned to service October 24, 1989, at 0137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br />. The radiation monitor was taken out of service again for maintenance on October 24, 1989, at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> and returned to service October 25, 1989, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. During both maintenance activities the Containment Purge was isolated.

Subsequent review showed radiation monitor RM8262 was taken out of service on October 21, 1989, for calibration under procedure SP 2404AL. Restoration from the procedure failed to open sample inlet isolation valve 2-AC-S2.

Therefore no operable Containment Atmosphere - Particle/Gaseous radiation monitor was available for 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />. During this period of time, Containment Puree was in service for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and isolated for 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />.

Below is the sequence of events, starting at the date Radiation Monitor RMS262 was calibrated, to the date the isolation valves were found closed.

10/21/89 time unknown RMS262 calibration, isolation valves closed 10/23/89 at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br /> "A" Diesel secured, RMS123 inoperative.

10/23/89 at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br /> Secured Containment Purge 10/24/89 at 0137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br /> Started Containment Purge 10/24/89 at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> Secured Containment Purge 10/25/89 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> Started Containment Purge 10/25/89 at 1849 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.035445e-4 months <br /> RMS262 isolation valves found closed Technical Specification Limiting Condition for Operation 3.3.3.1 titled "Radiation Monitoring," and 3.3.2.1 titled "Engineered Safety Feature Actuation System Instrumentation" were not entered.

Limi(ing condition for Operation 3.3.3.1 requires a grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the use of a constant air monitor. Limiting Condition for Operation 3.3.2.1 requires the Containment Purge Valves to be maintained in the closed position.

It should be noted that Health Physics conducted routine outage grab samples of Containment atmosphere with no unusual results during the time the sample inlet isolation valve 2-AC-82 was closed. Also an area radiation monitor is located in Containment on the refuel bridge which continuously monitors the Containment area.

The sample inlet isolation valve 2-AC-S2 was opened and radiation monitor RMS262 was declared operable.

NRC Form 366A (6-69)

NRC Form.366A U.S. NUCLEAR REGULATORY CO)i/JWSSION APPROVED OMB NO. 3150&104 (5-89) EXPIRES: 4/30/62 Estimated burden per response to comply with this LICENSEE EVENT REPORT (LER) information collection request: 50.0 hrs. Forward comments regarding burden estirna1e 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). Ofhce of Management and Budget. Washington. DC 20503, FACILITY NAME (1) DOCKET NUIVIBER (2) LER NUMBER I6l PAGE (3)

'+g'j YE AR C". SGl/ENttAL 14)MBER Millstone Nuclear Power Station Unit 2 0 5 0 0 0 3 3 6 8 9 0 0 9 0 1 0 3OF 03 TEXT (If more space is required. use additlOnal NRC Form 366A's) (tr)

During the performance of the calibration procedure SP 2404AL, valve 2-AC-S2 was closed.

During the performance of the rest of the procedure, it was determined by the person performing the calibration that a change to the way the radiation monitor was isolated was appropriate. The new isolation method provided in change 1 to procedure SP 2404AL called for the closure of the radiation monitor inlet valve, 2-AC-70, and radiation monitor outlet valve, 2-AC-74, by Operations. This change moved the isolation boundary from the inside the recirculation line on the skid to outside the recirculation line.

When the change was implemented and the isolation boundary moved, 2-AC-82 was not reopened.

The calibration activity was then completed by different personnel. They performed the procedure guidance provided by the change to have operations re-open valve 2-AC-70 and 2-AC-74. This completed the activities required by the procedure but left the radiation monitor isolated by the closure of valve 2-AC-S2.

The root cause of this event is personnel error. Prior to making a procedure change, valve 2-AC-S2 should have been opened, which would have restored the radiation monitor RM8262 valve lineup to normal operation. Once restored and the procedure change approved, the surveillance could have been completed using the new isolation boundary.

This event is being reported pursuant to the requirements of paragraph 50.73(a)(2)(i) which requires reporting of any operation prohibited by the plant's Technical Specifications. During the time radiation mon)tor RMS262 was isolated, radiation monitor RM8123 was in service without its emergency power source and would have performed its safety function, which is to isolate Containment Purge on a high radiation signal. During the time radiation monitor RM8123 was secured for maintenance, the Containment Purge was isolated.

Health Physics personnel conducted routine outage grab samples of Containment atmosphere during this period with no unusual results. Also, an area radiation monitor is located in Containment on the Refuel Bridge which continuously monitors the Containment area. Although, the Limiting Condition for Operation, LCO, (3.3.3.1) tvas not-entered, the actions required by the LCO were being performed.

Therefore, there are no safety consequences as a result of this occurrence.

Immediate action taken was to open isolation valve 2-AC-82, restoring sample flow, which restored radiation monitor RM8262 to operable status. The error of making changes to procedures prior to restoring the system to original conditions has been discussed with the personnel involved, and as a topic for the entire Instrument and Control department.

Also steps have been added to the restoration section of calibration procedure SP 2404AL and SP 2404AM which mll verify positive sample flow indication at the radiation monitor skid and verify no low flow or high flow alarms exist.

I I No similar events.

EIIS Codes ( )

IL - Radiation Monitoring System NRC Form 366A (6-8g)

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