HNP-96-020, Number of Personnel & Man-Rem by Work & Job Function,1995
| 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) | |
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CATEGORY ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9603010102 DOC.DATE: 8&/3.-2@32:
NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME-AUTHOR AFFILIATION ROBINSON,W.R.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFIIIATION DOCKET 05000400
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
NOTES:Application for permit renewal filed.
t by Fun 05000400 RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACNW NMSS/SCDB/SSSS RES/RPHEB EXTERNAL: LITCO BRYCE,J H
NRC PDR COPIES LTTR ENCL 1
0 6
6 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME LE,N
<<FILE CENTER NR PERB/B RGN2 01 NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 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 PO Box 165 New Hill NC 27562 FEB 21 1996 United States Nuclear Regulatory Commission AITENTION: Document Control Desk Washington, DC 20555 William P.. Robinson Vice President Harris Nuclear Plant SERIAL: HNP-96-020 SHEARON HARRIS NUCLEARPOWER 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 HARRiS PLANT NUMBER OF PERSONNEL 100 MREM JOB FUNCTION, TOTAL 1995 MAN-REM WORK AND JOB FUNCTION STAT UTIL CNTR STAT UTIL CNTR REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL ROUTINE MAINTENANCE MAINTENANCE PERSONNEL OPERATINO PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL Et{GZNEERZNO PERSCttNEL ZNSERVICE INSPECTION MAINTENANCE P ERSONNEL OPERATZNO PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL SPECIAL MAINTENANCE MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENOZNEERING P ERSONNEL WASTE PROCESSING MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENGINEERING P ERSONNEL REFUELING MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL TOTAL HAZNTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHYSICS PERSONNEL SUPERVISORY PERSONNEL ENOZNEERINO PERSONNEL 2
0 2
1 8
0 19 0
6 0
0 0
0 8
0 0
0 3
0 0
8 0
0 0
0 8
0 0
G 0
2 8
0 0
0 0
8 8
8 8
0 0
0 8
8 13 8
37 1
8 0
18 G
8 0
8 0
1 8
2 G
8 0
0 8
8 G
0 r~g 47 4
182 12 0
1 17 8
28 8
0 4
15 8
133 65 4
144 14 0
1 48 8
26 8
8 16 8
136 0.432 2.319 4.979
- 0. 106
- 0. 322
- 1. 775 G. 192 0.580 0
~ 813 0.287 G.294 O.GGG 8.832 0.008 G.084 5.726 G,391 2.851 O.G18 8.431 8.498 8.098 1.428 G.GGG G.G19 14.489 4.671 5.613 0,408 5.648 23.286 7.671 15.475 0.545 6.791 G.GGG G.GGG 8.032 0.803 0.821 0.026 G.GGB G.GGB O.GGG 0.887 0.835 G.'OGG G.GGG G'.GGG 0.881 G.GGG G.GGG G.GGG G.OBG G.GG1 G.GGG G.GGG 8 ~ GBB G.GGG G ~ GGG 8.941 G.GGG G.GB2 8.062 0.386 1.882 G.GOG 8.034 8.865 8.416 8.589 8.247 2.064 0.012 8.827 2.044 0.805 G.G18 0.815 G. 129 0.012 G.GG1 G.GGG G.OGG G.OGB 18.778 0.038 0.895 G.BOG 8.468 8.239 G.OOB G.B72 G.GGG G. 189 36.067 8.641
- 5. 168 1.357 65.944 49.649 8.924 7.417 1.384 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 COOLANTIODINESPIKES 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.
Acontact 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.