ML18012A147

Number of Personnel & Man-Rem by Work & Job Function,1995. W/960221 Ltr

ML18012A147
Person / Time
Site:	Harris
Issue date:	12/31/1995
From:	Robinson W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-96-020, HNP-96-20, NUDOCS 9603010102
Download: ML18012A147 (5)

Text

~ CATEGORY ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9603010102 DOC.DATE: 8&/3.-2@32: NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME- AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFII IATION

SUBJECT:

"Nu ber of Personnel & Man-Rem by Work & Job Function,1995."

W 960221 ltr.

DISTRIBUTION CODE: IE56D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 20.407 Annual Personnel Monitoring Rpt/Annual Rad Exposure R t by Fun 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 0 LE,N 1 1 INTERNAL: ACNW 6 6 <<FILE CENTER 1 1 NMSS/SCDB/SSSS 1 1 NR PERB/B 1 1 RES/RPHEB 1 1 RGN2 01 1 1 EXTERNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1 1 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T N"ED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 15

Carolina Power & Light Company William P.. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-96-020 FEB 21 1996 United States Nuclear Regulatory Commission AITENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 ANNUALOPERATING REPORT - 1995 Gentlemen:

In accordance with Harris Nuclear Plant Technical Specification 6.9.1.2, Carolina Power & Light Company herewith submits the annual report of (a) individuals receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions, (b) primary coolant iodine spikes, and (c) challenges to the pressurizer power-operated relief valves (PORVs) and safety valves for 1995.

Questions regarding this matter may be referred to Mr. T. D. Walt at (919) 362-2711.

Sincerely, MGW c: Mr. S. D. Ebneter Mr. N. B. Le Mr. D. J. Roberts Ms. M. L. Thomas OlOO32 96030iOi02 95i23i PDR ADQCK 05000400 R PDR State Road1134 NewHill NC Tel 919362-2502 Fax 919362-2095

Document Control D

<HNP'-96-020/ Page 2 RZMS ZI NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION, 1995 HARRiS PLANT NUMBER OF PERSONNEL > 100 MREM TOTAL MAN-REM WORK AND JOB FUNCTION STAT UTIL CNTR STAT UTIL CNTR REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE PERSONNEL 2 0 2 0.432 G.GGG 8.589 OPERATING PERSONNEL 1 8 0 2.319 G.GGG 8.247 HEALTH PHYSICS PERSONNEL 19 0 6 4.979 8.032 2.064 SUPERVISORY PERSONNEL 0 0 0 0. 106 0.803 0.012 ENGINEERING PERSONNEL 0 8 0 0. 322 0.821 8.827 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 0 0 3 1. 775 0.026 2.044 OPERATINO PERSONNEL 0 0 8 G. 192 G.GGB 0.805 HEALTH PHYSICS PERSONNEL 0 0 0 0.580 G.GGB G.G18 SUPERVISORY PERSONNEL 0 8 0 0 813

~ O.GGG 0.815 Et{GZNEERZNO PERSCttNEL 0 G 0 0.287 0.887 G. 129 ZNSERVICE INSPECTION MAINTENANCE P ERSONNEL 2 8 0 G.294 0.835 0.012 OPERATZNO PERSONNEL 0 0 0 O.GGG G.'OGG G.GG1 HEALTH PHYSICS PERSONNEL 8 8 8 8.832 G.GGG G.GGG SUPERVISORY PERSONNEL 8 0 0 0.008 G'.GGG G.OGG ENGINEERING PERSONNEL 0 8 8 G.084 0.881 G.OGB SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 13 8 37 5.726 G.GGG 18.778 OPERATING PERSONNEL 1 8 0 G,391 G.GGG 0.038 HEALTH PHYSICS PERSONNEL 18 G 8 2.851 G.GGG 0.895 SUPERVISORY PERSONNEL 0 8 0 O.G18 G.OBG G.BOG ENOZNEERING P ERSONNEL 1 8 2 8.431 G.GG1 8.468 WASTE PROCESSING MAINTENANCE PERSONNEL G 8 8.498 G.GGG 8.239 OPERATING PERSONNEL 0 0 8.098 G.GGG G.OOB HEALTH PHYSICS PERSONNEL 8 8 1.428 8 ~ GBB G.B72 SUPERVISORY PERSONNEL G 0 G.GGG G.GGG G.GGG ENGINEERING P ERSONNEL r~g G.G19 G ~ GGG G. 189 REFUELING MAINTENANCE PERSONNEL 47 4 182 14.489 8.941 36.067 OPERATING PERSONNEL 12 0 1 4.671 G.GGG 8.641 HEALTH PHYSICS PERSONNEL 17 8 28 5.613 G.GB2 5. 168 SUPERVISORY PERSONNEL 8 0 4 0,408 8.062 1.357 ENGINEERING PERSONNEL 15 8 133 5.648 0.386 65.944 TOTAL HAZNTENANCE PERSONNEL 65 4 144 23.286 1.882 49.649 OPERATING PERSONNEL 14 0 1 7.671 G.GOG 8.924 HEALTH PHYSICS PERSONNEL 48 8 26 15.475 8.034 7.417 SUPERVISORY PERSONNEL 8 8 0.545 8.865 1.384 ENOZNEERINO PERSONNEL 16 8 136 6.791 8.416 66.757 GRAND TOTAL 143 4 311 53.688 1.517 126. 131 Notes: (I) Dose based on electronic dosimeters (2) STAT=Harris Plant staff UTIL=CP&L non-Harris personnel CNTR= Contractor (3) Special Maintenance includes special work on spent fuel cask, spent fuel pools, moveable in-core detectors seal table room equipment, steam generators, reactor head, and certain valves and pumps.

Docuinent Control Des BNP-96-020/ Page 3 1995 ANNUALREPORT - PRMARY COOLANT IODINE SPIKES During 1995, the primary coolant did not exceed 1.0 pCi/gram dose equivaient I-131 or 100/E-bar pCi/gram gross radioactivity as set forth in Technical Specification 3.4.8.

Docuraent Control Des HNP-96-020/ Page 4 1995 ANNUALREPORT - PRESSURIZER RELIEF AND SAFEIY VALVE CHALLENGES There were no challenges to the pressurizer safety valves in 1995. One (1) pressurizer power-operated relief valve was challenged in 1995. Details of this event are described below.

On November 5, 1995, with the plant operating in Mode-1 at 100% power, A-Train Engineered Safety Feature Actuation System (ESFAS) slave relay surveillance testing was in progress. While performing the test portion that verifies the operability of the Main Steam Line Isolation Signal circuitry, a "Low Steam Line Pressure Reactor Trip/Safety Injection (Sl)" signal was generated.

A contact on the K809 relay failed to maintain continuity eliminating the "block" function to the "A" Main Steam Isolation Valve (MSIV). As the valve closed and turbine throttle valve position remained constant, increased steam load was carried by "B" and "C" Steam Generators. This resulted in a pressure decrease in the "B" and "C" main steam lines due to increased steam flow.

The rate compensation feature associated with the low steam line pressure SI initiated a low steam line pressure Reactor Trip/SI Signal for "C" steam line.

Due to the SI, the Reactor Coolant System (RCS) was being filled to solid plant conditions by the injection flow. The main control room operators proceeded through the Emergency Operating Procedure (EOP) network as required to secure SI. Although progress through the EOP procedure flow paths was timely, it did not prevent the plant from going solid. The solid plant conditions insulted in an increase in RCS pressure, which lifted pressurizer power-operated relief valve (PORV) PCV-444B. A liquid/steam mixture was released by the pressurizer PORV to the Pressurizer Relief Tank (PRT). During this time the PORV cycled approximately 58 times. This resulted in an overpressure condition in the PRT and one of the two rupture disks ruptured.

Approximately 1200 gallons qf water from the PRT'spilled into the containment sump. The control room staff took actions necessary to stabilize the plant and establish Mode-3 (Hot Standby). An Unusual Event (UE) was declared at 0805 due to the Emergency Core Cooling System actuation. The UE was exited at 0912 upon termination of SI and stabilization of the plant in Mode-3.

An inspection and evaluation were performed to assess the condition of PORV PCV-444B. It was concluded that PCV-444B was acceptable for plant restart and power operations.

A more detailed description of this event was reported in Licensee Event Report (LER)95-011, dated December 5, 1995.