05000293/LER-1993-008
| ML20056C233 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/04/1993 |
| From: | Boulette E, Gay R BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-59, LER-93-008, LER-93-8, NUDOCS 9305120031 | |
| Download: ML20056C233 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| 2932093008R00 - NRC Website | |
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55 10 CFR 50.73 BOSTON EDISON P8gnm Nucicar Power Station Rocky Hill Road Plymouth, Massachusetts 02360 May 4 , 1993 BEco Ltr. 93- 59 E. T. Boulette, PhD Senior Vce President - Nuclear U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Docket No. 50-293 License No. DPR-35
Dear Sir:
The enclosed Licensee Event Report (LER) 93-008-00, " Failure to Perform Functional ,
Test of Control Room High Efficiency Air Filtration System Humidistats in 1990", is submitted in accordance with 10 CFR Part 50.73.
Please do not hesitate to contact me if there are any questions regarding this report.
E. T. Bou'ette k
RAG /bal
Enclosure:
LER 93-008-00 cc: Mr. Thomas T. Martin Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd.
King of Prussia, PA 19406 Mr. R. B. Eaton Div. of Reactor Projects 1/II Office of NRR - USNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 Sr. NRC Resident Inspector - Pilgrim Station Standard BECo LER Distribution t
9305120031 930504 gDR- ADOCK 0500 3 . gy
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 ts-82) EXPIRES 5/31/95 ESTAuTED BURDEN PER RESPONSE TO COMPLY W'T H THIS iNF ORMA')ON COLLECTION REQUEST. 5:Le HMS. FORWARD LICENSEE EVENT REPORT (LER) COyuEms ataARDua adRDEN EsmuTE TO THE ,,OnM.TcN AND RECORDS MANAGEVENT MANOH IMNBB 7714L U S. NUCLEAR HEGULATORY COMM$S.lON. W ASHINGTON, DC 20555 0301. AND TO THE FAPERW34al FCDUCTION P40 JECT (343-c?c.11, office OF ,
(See reverse for required number of dgts ' characters for each blocit) MANA3EMENT AND Bu:xiET, w'AsHjNGTON, DC 20503.
Pilgrim Nuclear Power Station O 000 293 1$F%
inu t4) Failure to l'erlorm f unctional lest of Control 1,oom di6 u LAlicieuuj Au 1.tl u ur icu
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System Humidistats in 1990 .
EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) .
uDNTH DAY YEAR YEAR MONTH DAY YEAH 00 F AQUlv NAME DOCKET NUMBER 4 9 93 g 93 008 00 05 04 93 , N/A 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: fCheek one or more) (11) ,
MODE (9) N 20.402ib) 20 405tc) 50.73 a):2)(iv) 73.71(b) i POWER 20 405(a)(1)(:) 50.30(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL (10) 94 20 405(a)(1)(u) 50 35(c)(2) 50.73(a)(2)(vu) OTHER f 20 405fa)(1)(di) X 50 73(a)(2)(i) (b) 50 73(a)(2)(vm)(A) >#y e Abwaci 20 405;a)(1)(iv) 50 73(a)(2)(n) 50.73(a)(2)(vin)(B) a
, 20 405(a)(1)(v) 50.73(a)(2)(m) 50.73(a)(2Hx)
LICENSEE CONTACT FOR THIS LER (12)
Robert A. Gay - Senior Compliance Engineer "]"} ^** "" i COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED 1N THIS REPORT (13) cAUSE S C[ U COWGNEN' U AN$ AO URE A g CAUSE SYSTEM COMPONENT MANur ACTUREA l
SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED "*" UAV *^* ,
vEs SUBMISSION i er ymee ExPEcTEo sassoN ccE; X DATE (15) ,
On April(Qm:t ABSTRACT 9, 1993, to 1400 it was spaces. determine Le , approximately 1p sin $!e sbaced tySewrcten lineQ (16)t at t e Control Room High E .
Filtration System Relative Humidity Switches (Humidistats) had not been functionally !
tested once-per-cycle as specified by Technical Specification 4.7.B.2.d. j Specifically, the relative humidistats had not been functionally tested during the '
period July 1, 1988, to January 23, 1992. This period, in excess of 42 months, i exceeds the once-per-cycle definition in Technical Specifications. .
The cause was utility non-licensed p2rsonnel error in the non-performance of the i functional test and subsequent review of Procedure 8.E.47.1, conducted on March 10, t 1990. An Instrumentation and Control (I&C) supervisor signed-off the Master !
Surveillance Tracking Program for performance of the functional test when a portion !
of the test was not performed. Initial action taken included I&C verifying the performance of the functional test on January 23, 1992, with satisfactory as-found results. Corrective Action taken includes training for I&C Supervisor review of r completed surveillance procedures. 'l The discovery occurred during power operation while at 94 percent power. The reactor ;
mode selector switch was in the RUN position. The Reactor Vessel (RV) pressure was '
1015 psig with the RV water temperature at 520 degrees Fahrenheit. This report is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B). This event posed no threat to ;
the public health and safety. ,
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REQUIRED NUMBER OF DIGITS / CHARACTERS FOR EACH BLOCK .
BLOCK NUMBER OF NUMBER DIGITS / CHARACTERS 1 UP TO 46 FACIUTY NAME 2 DON MBR 3 IN ADDITION 10 05000 3 VARIES PAGE NUMBER I
4 UP TO 76 TITLE
{ 6 TOTAL 5 E M DATE 2 PER BLOCK 7 TOTAL 6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 7
2 PER BL CK UP TO 18 - F ACILITY NAME 8 ^
8 TOTAL - DOCtGT NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE 10 3 POWER LEVEL l
'l REQUIRENEmS OF 10 CR CHECK BOXTHAT APPUES P TO 50 FOR NAME 12 UCENSEE CONTACT 14 FOR TELEPHONE CAUSE VAR!ES 2 FOR SYSTEM i 13 4 FOR COMPONENT EACH COMPONENT FAILURE i 4 FOR MANUFACTURER l NPRDS VARIES I4 CHECK DOX THAT APPUES 15 ECTED SUBM!SSION DATE 2 PER BLOCK l
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05000 293 2OF5 Pilgrita Nuclear Power Station 93 008
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,w w - u n a - .. ~ . n .,euu w x m m) l Th Co tr 1 Room High Efficiency Air Filtration (CRHEAF) System consists of two separate, manually-controlled trains. Each train consists of an air-operated damper, l a filter unit, a supply fan, and a manually-adjustable damper that establi:.hes the CRHEAF System flowrate of air to the Control Room. As a result of a manual start of ;
a CRHEAF System train (s), the normal air supply is diverted by the automatic !
repositioning of the air-operated dampers, operation of the CRHEAF System supply !
fan (s), and the introduction of high efficiency particulate and charcoal filtered air
- to the Control Room at a positive pressure (relative to the adjacent areas). The system is initiated if the normal supply of monitored air becomes contaminated. The relative humidity switches (humidistats) RHS-1A and IB function to maintain humidity less than or equal to 70 percent such that the charcoal filters can perform their '
safety functions.
EVENT DESCRIPTION l On April 9,1993, it was determined that the CRHEAF System Humidistats had not been functionally tested once-per-cycle as specified by Technical Specification 4.7.B.2.d. -
Specifically, the relative humidistats RHS-1A and -1B had not been functionally {
tested during the period July 1, 1988, to January 23, 1992. This' period, in excess !
of 42 months, exceeds the once-per-cycle definition in Technical Specifications.
The discovery occurred on April 2,1993, as a result of Quality Assurance Department i Audit #93-03. The Quality Assurance engineer was reviewing CRHEAF System ;
surveillances as performed in accordance with Procedure 8.E.47.1, Control i Room /Radwaste Filtration System Instrumentation Calibration / Logic Functional Test". :
During review of Procedure 8.E.47.1, performed on March 10, 1990, the engineer discovered that Section 2.3 of Attachment I and 2 was not performed causing humidistats RHS-1A and -1B not to be functionally tested. The date for the last ;
f unctional test of the humidistats was July 1,1988, and the next acceptable [
completion date for the functional test was January 23, 1992. The engineer contacted i the Instrumentation and Control Division that perform the surveillance test. !
Subreluent investigation revealed calibration and functional testing of the relative ,
humidtstats had not been performed since July 1,1988. Problem Report 93.0204 was-written on April 2,1993, and Deficiency Report 2019 was issued on April 22, 1993, to ;
document the discovery. r The discovery occurred during power operation with the reactor mode selector switch j in the RUN position. The reactor power level was 94. percent. The Reactor Vessel
.(RV) pressure was 1015 psig with the RV water temperature at 520 degrees Fahrenheit. ;
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CAUSE The cause was utility non-licensed Instrumentation and Control Division Technician [
and Supervisor personnel error. The error involved not performing the functional test and subsequent review of Procedure 8.E.47.1 (Rev. 8), Attachment I and 2, .
" Control Room High Efficiency Filtration System-Train A (Train B) - Instrumentation '
Calibration and Logic Functional Test-Panel C-108 (C-109), performed on March 10, 1990. The supervisor mistakenly accepted the steps that were incorrectly i marked as not performed (N/P). The supervisor signed MSTP node 3361 (Attachment 1) :
and node 3362 (Attachment 2) even though the functional test of humidstats RHS-1A and
-1B had not been performed. ,
A factor contributing to the error was the way that step 2.3[1] of Attachments 1 and 2 were interpreted. Step 2.3[1] directed the technician as follows: "If Section 2.2.
was not performed, record the as-found dial setting of relative humidistat or N/A ;
step". This lead to all remaining substeps of Section 2.3 to be entered with an N/A. l CORRECTIVE ACTION I Instrumentation and Controls verified Procedure 8.E.47.1 (Rev. 12), Attachments 1 and 2, was performed on January 23, 1992, with satisfactory as-found results. The !
procedure was properly performed, reviewed and nodes 3361 and 3362 were signed-off ,
accordingly. The satisfactory as-found results of the surveillance test provides assurance that humidistats RHS-1A and -1B were operable during the period they had not been surveillance tested. j Prior to performance on January 23, 1992, Procedure 8.E.47.1 had been revised via the normal revision process. Step 2.3 [1], which is now step 2.2 [1], was enhanced to read: "If Section 2.1 was not performed, record the a;-found dial setting of relative humidistat or enter not performed (N/P) for this step" As evidenced by satisfactory '
performance of Procedure 8.E.47.1 (Rev. 12), on January 23, 1992, the remaining substeps of Section 2.2. were properly performed.
The Instrumentation and Control Division Technicians and Supervisors have been made aware of the error and understand performance of Procedure 8.E.47.1 for functional testing the humidistats is required once-per-cycle as specified by Technical Specification 4.7.B.2.d. ,
As part of the corrective actions in reply to NRC Notice of Violation (50-293/92 01) I&C Supervisors received training for I&C Supervisor review of completed surveillance procedures. The training, conducted on February 1, 1993, focused on I&C Supervisor responsibilities and management expectations regarding completed surveillance procedures. Essentially, the I&C Supervisor is responsible for ensuring a completed surveillance procedure has been properly conducted prior. to review / signature by the senior utility shift licensed operator (NWE). .
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- mJrv NAME (1) l DOCKET NUMBER (2) LER NUMBE R (S) PAGE (3) gp blGVEN16AL REifSON Pilgrim Nuclear Power Station 05000293 4 or 5 93 ,, 008 00 T w m . w.c. . w n. .. - - .? w = n,m n m pro Included in this I&C Supervisor responsibility are checks that include information/ data entry where required, comparison of data entered to identified tolerances, appropriateness when a step is not performed, legibility, and explanation of notes or discrepancies in the proper location.
The effectiveness of the I&C Supervisor training is being assessed. Initially, I&C Supervisors will complete a yes-no type checklist containing key elements directly related to the training conducted. The completion date for all current I&C Supervisors is expected to be September 1, 1993.
The longer term effectiveness of the training conducted will also be assessed via a periodic sample of completed surveillance procedures. The earliest completion date would be the end of January 1994.
SAFETY CONSE0VENCES This condition posed no threat to the public health and safety.
The missed functional test of the relative humidistats was not a component failure.
The CRHEAF System is required to be operable whenever the reactor is critical and during refueling operations. The satisfactory as-found results of the functional test of the humidistats on January 23, 1992, provides assurance that the humidistats were operable during the period they had not been functionally' tested as specified by Technical Specification 4.7.B.2.d.
This report is submitted in accordance with 10 CFR 50.73 (a)(2)(i)(B) because the relative humidistats had not been functionally tested once-per-cycle as specified by Technical Specification 4.7.B.2.d.
SIMILARITY TO PREVIOUS EVENTS A review was conducted of Pilgrim Station Licensee Event Reports (LERs). submitted since January 1984. The review focused on LERs submitted in accordance with 10 CFR
- 50. 73(a)(2)(i) involving a missed surveillance test due to personnel error. The review identified related instances reported in LERs 50-293/91-002-00 and 92-012-00.
For LER 91-002-00, a once-per-three month surveillance test of one of the five Salt-Service Water System pumps was not performed within the interval specified by Technical Specification 4.5.B.1.b. A proctdure error resulted in signing the MSTP node for the pump even though the pump had not been tested.
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 Es2) EXPIRES 5/31/95 ESTMATED BJRDEN PER RESPONSE TO COMPLY WTH THt$
INFORMATON Cou.ECTON FIEQUEST: 50.0 HRS. FoRWAEC LICENSEE EVENT REPORT (LER) couMEuTS REGeoNG BuRoEN EsTuct To TsE iN oRuiTON AND RECORDS MANAGEMENT BRANOH p/NBB 77141.U.S NJ0 LEAR TEXT CONTINUATION REGautoRv CoMu:ssON. wAss>NcToN. oc 2asss.mi. ANo To THE PAPERWORK REDUCTON PRCilECT (31534104), OFF4CE of MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
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SEQJEN%AL REV BON NUMBER NUMBER 05000 293 5 oF 5
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For LER 92-012-00, a once-per-cycle calibration test of the Neutron Monitoring System Recirculation Flow Converters was not performed within the interval specified by Technical Specification 4.2.C. The MSTP nodes for performance of the calibration and functional test were signed-off by a supervisor when only the functional test had been performed.
ENERGY INDUSlRY IDENTIFICATION (Ells) CODES COMPONENTS CODES Switch, Moisture (RHS-1A and IB) MS SYSTEMS Control Complex Environmental Control (CRHEAF) System VI t
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