ML18022A963

From kanterella
Jump to navigation Jump to search
LER 95-005-00:on 950731,TS Violation Occurred Due to Missed Compensatory Vent Stack Flow Rate Estimate.Counseled Individual Involved & Training for Appropriate Operations Personnel Will Be performed.W/950828 Ltr
ML18022A963
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/24/1995
From: Donahue J, Verrilli M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-950694, LER-95-005-02, LER-95-5-2, NUDOCS 9509050219
Download: ML18022A963 (6)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9509050219 DOC.DATE: 95/08/24 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina O5OOO4OO P AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.

DONAHUE,J.W. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 95-005-00:on 950731,TS violation was discovered due to missed compensatory vent stack flow rate estimate. Counseled individual involved.W/950828 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS 1 1 ~AEOD/-SRD~B~ 2 2 AEOD/SPD/RRAB 1 1 PI=&& CENTE~ 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DRCH/HHFB 1 '1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPSB/B 1 " 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY NARD 1 1 LI TCO BRYCE I J H 2 2 C NOAC MURPHY I G A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL~

DESK, ROOM OWFN 5D8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

I FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27

Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 AUG 28 1995 Letter Number: HO-950694 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 95-005-00 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.

Sincerely, J. W. Donahue General Manager Harris Plant MV Enclosure Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - PM/NRR)

Mr. S. A. Elrod (NRC - SHNPP)

Mr. W. R. Robinson 950'st050219 950824 PDR

...B...

ADOCK 05000400 PDR.

State Road 113k New Hill NC ggk'

U. S. Nuclear Regulatory Commission Page 2 cc: Ms. D. B. Alexander Mr. W. R. Campbell (BNP)

Mr. J. M. Collins Mr. J. P. Cowan Ms. S. D. Floyd Mr. H. W. Habermeyer, Jr.

Ms. T. A. Head (GLS File)

Mr. G. D. Hicks Mr. M. D. Hill Mr. R. M. Krich (RNP)

Mr. P. M. Odom (RNP)

Mr. C. W. Martin (BNP)

Mr. R. D. Martin Admiral K. R. McKee Mr. J. P. McKone Mr. J. W. Moyer (RNP)

Mr. G. A. Rolfson Mr. C. T. Sawyer Mr. R. S. Stancil Mr. J. P. Thompson (BNP)

Mr. T. D. Walt HNP Real Time Training INPO NLS File: HI/A-2D (L. M. Randall)

NRC FORM (5-92) 366 e

LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COHHISSION PROVED BY OHB NO.

ESTIHATEO BURDEN EXPIRES 5/31/95 3150-0104 PER RESPONSE TO COMPLY WITH EST: 50.0 HRS.

THIS INFORHATION COLLECTION RE FORWARD C(NNENTS REGARDING BURDEN ESTIHATE TO THE INFORHATION AND RECORDS NNAGEHENT BRANCH (See reverse for required number of digits/characters for each block) (HNBB 7714). U.S. NUCLEAR REGULATORY CONISSION.

WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) . OFFICE OF HANAGEMENT AND BUDGET WASHINGTON. DC 20503.

FACILITY NAHE (1) DOCKET NUHBER (2) PAGE (3)

Shearon Harris Nuclear Plant-Unit ¹1 05000/400 1 OF 3 TITLE (4) Technical Specification Violation due to missed compensatory vent stack flow rate estimate.

EVENT DATE (5) LER NUHBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (B)

REVISION FACILITY NAHE DOCKET NU%ER SE(IUENTIAL NONTH DAY YEAR UHBER NUHBER DAY YEAR 05000 FACILITY NAYiE DOCKET NUMBER 07 31 95 95 005 00 24 95 05000 OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE RE UIREHENTS OF 10 CFR S: (Check one or more) (ll)

NODE (9) 20.402(b) 20.405(c} 50.73(a)(2)(iv) 73.71(b)

POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73<a)(2)(v) 73.71<c) 100K 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii)

LEVEL (10) OTHER 20.405(a)(l)(iii) Z 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(l)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract and in Text.

below 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)

LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUHBER (Include Area Code)

Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM C(NPONENT HANUFACTURER CAUSE SYSTEH CIIPONENT HANUFACTURER TO NPRDS TO NPRDS SUPPLEHENTAL REPORT EXPECTED (14) EXPECTED NON TH DAY YEAR YES SUBHISSION

( If yes. complete EXPECTED SUBMISSION DATE). X NO DATE (15)

ABSTRACT (Limit to 1400 spaces. i.e., approximately 15 single-spaced typewritten lines) (16)

On July 31, 1995, preparations were in progress for performing surveillance testing on the Waste Processing Building Stack 5A effluent radiation monitor. During these preparations the Senior Control Operator (SCO) coordinating the test evolution in the main control room, overlooked procedural guidance indicating that the associated vent stack flow rate monitor should be declared inoperable. Due to this, the Stack 5A Flow Rate Monitor was not declared inoperable and the compensatory 4-hour flow rate estimates required by Technical Specification 3.3.3.11 were not performed.

This condition was identified at approximately 1800 that evening, during the shift turnover process in the main control room when the operability status of the stack 5A flow rate monitor was questioned by the on-coming SCO. Flow estimates were commenced immediately upon realizing the problem. This condition was caused by personnel error on the part of the Operations individual coordinating the testing evolution in the main control room. Corrective actions included counseling this individual. Training for appropriate operations personnel will also be performed.

One similar LER (¹94-002) was submitted on August 16, 1994.

NRC FORH (5-92) 366A LICENSEE EVENT REPORT (LER) t APPROVED BY OHB NO.

ESTIHATED BURDEN FORWARD CONENTS EXPIRES PER 3150-0104 5/31/95 RESPONSE TO THIS INFORMATION COLLECTION REQUEST:

COMPLY WITH 50.0 HRS.

REGARDING BURDEN ESTIHATE TO THE INFORMATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714). U.S. NUCLEAR REGULATORY COMMISSION.

WASHINGTON. DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF HANAGEHENT AND BUDGET. WASHINGTON. DC 20503.

FACILITY NAHE (1) DXKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL REVISION NUHBER NUHBER Shearon Harris Nuclear Plant - Unit ¹1 05000/400 20F 3 95 005 00 TEXT (1f more space is required, use additional copies of NRC Form 366A) (17)

EVENT DESCRIPTION:

On July 31, 1995, the plant was operating in Mode-1 at 100% power. At approximately 0730 that morning, preparations were in progress to perform MST-I0413 (Waste Processing Building Vent Stack 5A Flow Rate Monitor and Isokinetic Sampling System Calibration). Maintenance personnel contacted the Senior Control Operator (SCO) in the main control room to inform him that MST-I0413 was to be performed that morning.

The SCO was informed that the test would render the stack 5A PIG (Particulate, Iodine, and Gas) and WRGM (Wide Range Gas Monitor) radiation monitors inoperable. The SCO then used Operations Work Procedure (OWP-RM-18) to determine the required compensatory actions. Procedure OWP-RM-18 contains a caution step that states that if both the PIG and WRGM monitors are inoperable, the flow rate monitor must also be declared inoperable. This guidance was overlooked by the SCO coordinating the testing evolution. Prior to beginning the test, at 0920, the Stack 5A PIG and WRGM were declared inoperable and compensatory measures were implemented accordingly. It was not acknowledged at this point that the flow rate monitor should be declared inoperable.

During the shift turnover process that occurred in the main control room at approximately 1800 that evening, the on-coming SCO recognized that if a WRGM and PIG are declared inoperable, the associated stack flow monitor should also be declared inoperable. Questions into the scope of the testing and the operability status of the flow rate monitor revealed that the required flow rate estimates had not been performed, resulting in a violation of TS 3.3.3.11. The SCO immediately initiated the compensatory 4-hour flow estimates.

CAUSE:

This condition was caused by personnel error. The caution contained in OWP-RM-18 was overlooked by the SCO coordinating the testing evolution in the main control room during preparations for performing MST-I0413. This resulted in the Stack 5A Flow Rate Monitor not being declared inoperable as required and the subsequent failure to perform 4-hour compensatory flow rate estimates.

SAFETY SIGNIFICANCE:

The estimated flow values are used when increased effluent radioactivity levels are indicated by either the 12-hour grab samples or the auxiliary sampler. During the period of time on July 31, 1995, when the estimates were not taken, no abnormal. increase in radioactivity levels was indicated. The other function served by the 4-hour flow estimate is to provide a flow rate input for calculating the weekly gaseous effluent dose. During the performance of this calculation, if flow values are not available, the Chemistry Technician uses the weekly flow value provided by the isokinetic skid or a conservative high-flow default value.

Therefore, the failure to perform the 4-hour estimates resulted in no safety consequences.

/

NRC SO%I 366A U.S. NUCLEAR REGULATORY COHHISSION PPROVE Y NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD CONENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714). U.S. NUCLEAR REGULATORY COMMISSION.

WASHINGTON'C 20555-0001 AND TO THE PAPEfMRK REDUCTION PROJECT (3150-0104) . OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DXKET NUHBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVISION YEAR NUMBER NUMBER Shearon Harris Nuclear Plant - Unit ¹1 05000/400 3 OF 3 95 005 00 TEXT (If more space is required. use additional copies of NRC Form 366A) (17)

PREVIOUS SIMILAR LERs:

A similar LER (¹94-002) was submitted on August 16, 1994. Corrective actions taken for that event included revising procedure OWP-RM-18, to include radiation monitor operability guidance. Had the procedural requirements contained in OWP-RM-18 been followed, the recent event would have been prevented.

CORRECTIVE ACTIONS COMPLETED:

1. The involved SCO was counseled on the event.

CORRECTIVE ACTIONS PLANNED:

1. Training will be provided to appropriate personnel in the Operations Unit.

EIIS INFORMATION:

S stem Name/Code: Com onent Code:

Radiation Monitoring - IL Monitor - MON