05000282/LER-1993-012
| ML20057E750 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/08/1993 |
| From: | Richard Anderson, Hunstad A NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-93-012, LER-93-12, NUDOCS 9310130114 | |
| Download: ML20057E750 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| 2822093012R00 - NRC Website | |
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Northem States Power Company ,
414 Nicollet Mall .
Minneapohs, Minnesota 55401 1927 Telephone (612) 330-5500 i
October 8, 1993 10 CFR Part 50 Section 50.73 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Failure to Perform Offsite Dose and Effluent Monitor Setpoint 'l Calculations Due to Procedural inadeauacy aILd Personnel Error The Licensee Event Report for this occurrence is attached. In the report, we made the following new NRC commitments:
The monthly dose calculations and the monthly effluent monitor setpoint calculations are now being schec" led by the Chemistry Group's work i
scheduling program, and both calculations have also been added to the chemistry Group's surveillance program. These processes will schedule the l initiation, review and completion of both calculations. Radiation Protection Implementing Procedures have been revised to reflect the above changes.
The Radiation Protection and Chemistry Group is reviewing other areas that may depend on non-scheduled actions; any such actions found will be added to the work scheduling programs.
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US NRC October 8, 1993 Page 2 l
1 Please contact us if you require additional information related to this event.
2 Y W' Roger O Anderson Director Licensing and Management Issues I
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c: Regional Administrator - Region III, NRC 1 NRR Project Manager, NRC Senior Resident Inspector, NRC Kris Sanda, State of Minnesota ;
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1 Attachment 1
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I:RC FORM 366 U.S. NUCLEAR REGUL ATORY CtMMISSION APPROVED BY OMB wo. 3150-0104 (5-92) EXPIRES $/31/95 ESilMATED DURDEN PER RESPONSE TO COMPLY WITH LICENSEE EVENT REPORT (LER) $dD [(MMI'NIS RIG \RDIhGBURDEN ESil ATE b THE INFORMATION AND RECORDS MAN AGEME NT BRANCH (MNBB 7714), U.S. kUCLEAR REGULATORY COMMIS$10N, (See reverse f or required number of digits / characters for each block) WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGE T, WASHINGTON, DC 20503.
FAClllIY NAME (1) DOCKEY NUMBER (2) PAGE (3)
Prairie Island Nuclear Generating Plant U1 05000 282 1 OF 3 TITLE (4) Failure to Perf orm Of f site Dose and Ef fluent Monitor Setpoint Calculations Due to Procedural Inadequacy and Personnel Error IVINT DATE (5) LfR N!MBER (6) REPORT DATE (7) OTHER f ACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR TEAR " ^
NUMBER NUMBER Prairie Island U2 05000 306 09 08 93 93 --
12 --
00 10 08 93 0 0O OPE RAT I NG g THIS REPORT IS SUHMITTFD PURSUANT TO THE REQUIRE MF NTS OF 10 CTR b (Check one or more) (11)
MODE (9) 20.402(b) 20.405(c) 50. 73(a)(2 )( i v) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVIL (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vi i ) OTHER 20.405(a)(1)(tii) X $0. 73( a)(2)( t ) 50.73(a)(2)(viii)(A) (Specify in A t c ow 20.405(a)(1)(6v) 50.73(a)(2)(ii) 50.73(a)(2)(viti)(8) 20.405(a)(1)(v) 50.73(a)(2)(tii) 50.73(a)(2)(x) WaC Form 366A)
LICf kSf f CtmT ACT FOR THIS tf R (12)
AAME TELEPHONE NUMBEF (include Area Code)
Arne A Hunstad 612-386-1121 l CtmPL ETE CWE L INE IDR I ACH CtMPONINT F Allure DE SCRIHf D IN THIS RE PORT (13)
CAUSE SY ST E M COMPONEhi MANUFACTURER CAUSE SYSTEM COMPONE NT MANUFAC1UEER p SUPPL f Mf h T AL RE PORI E XPE CIf D (14) LXPECTED MONTH DAV YEAR TIS SUilMISSION (11 yes, complete EXPECTED SUlWISSION DATE). X WO DATE (15)
. ABSTRACT (Lireit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On September 8, 1993, the Radiochemistry Supervisor was reviewing the dose calculations for liquid and noble gas releases for the month of August 1993. During that review. he noted that the dose calculations due to radioactive releases of liquids and gases had not been completed for the month of July 1993. Further review showed that the monthly alarm setpoint
, calculations for liquid and airborne effluent monitors, which are normally performed at the same time as the dose calculations, were also not completed for the month of July 1993. The dose and setpoint calculations are required by Technical Specifications in accordance with methods specified in the Offsite Dose Calculations Manual.
Dose and setpoint calculations were performed on the July release data as soon as the oversight was detected. Those calculations ver ified that the
.! previous monitor setpoints were correct and that the doses to the public were very small at less than 0.2% of quarterly and annual dose limits.
The monthly dose calculations and the monthly effluent monitor setpoint calculations are now being scheduled by the Chemistry Group's work scheduling program, and both calculations have also been added to the Chemistry Group's surveillance program.
NEC IORM 366 (5-92)
l CRC FORM 3664 U.S. CUCLEAR REGULATO Y COMMISSI C APPROVED BY OMB No. 3150-0.J4 (5-92) EXPlRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE 10 LICENSEE EVENT REPORT (LER) THE IkFORMATION AND RECORDS MANAGEMENT BRANCH l TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND To THr ?APERWORK l REDUCTION PROJECT (3150-0104:, OFFICE OF MANAGEMENT AM BUDGET, WASHINGTON, DC 20503.
FACILITY NAMF (1) DOCKET NLMBER (?) LFR NUMRFR (61 PAGF (3) yggg SEQUENTIAL REVISION Pralrie Island Unit 1 NuusrR NumeER l 93 00 2 OF 3 05000 282 -- 12 --
TEXT (if more space is reautred. use additional copies of NRC Form 366Al (17) l EVENT DESCRIPTION l On September 8, 1993, the Radiochemistry Supervisor was reviewing the dose calculations for liquid and noble gas releases for the month of August 1993. During that review, he noted that the monthly dose totals and the '
current calendar quarter's cumulative totals were the same values.
Investigation of controlled records and the computer database showed that the dose calculations due to radioactive releases of liquids and gases had not been completed for the month of July 1993. The dose calculations are required by Technical Specifications 4.17.A and 4.17.B in accordance with methods specified in the Offsite Dose Calculations Manual.
Further review showed that the monthly alarm setpoint calculations for liquid and airborne effluent monitors, which are normally performed at the same time as the dose calculations, were also not completed for the month of July 1993. The setpoint calculations are required by Technical Specifications 3.9.E and 3.9.F in accordance with methods specified in the ,
Offsite Dose Calculations Manual. '
Dose and setpoint calculations were performed on the July release data as soon as the oversight was detected. Those calculations verified that the previous monitor setpoints were correct and that the doses to the public were very small at less than 0.2% of quarterly and annual dose limits.
CAUSE OF THE EVENT Primary causes of the event were lack of procedures and personnel error.
The required calculations were not scheduled by the Chemistry Group's work scheduling program and were not tracked by the Chemistry Group's surveillance program. The calculations are conducted on the Radiation Dose Assessment Computer and are completed by the Radiochemistry Supervisor.
The calculations are supported procedurally by Radiation Protection Implementing Procedures in the Count Room Manual. The computer generates all of the required documentation, so completion of standard surveillance forms seemed inappropriate.
Since the calculations have not been scheduled activities, it has been the responsibility of the Radiochemistry Supervisor to remember to complete the calculations each month after the previous month's effluent release
! sampling and analyses had been completed. He failed to perform the July calculations and that fact was not discovered until the August calculations were performed.
ANALYSIS OF THE EVENT This event is reportable pursuant to 10CFR50. 73 (a) (2) (i) (B) . Technical
s .
CRC FORM 366A U.S. OJCLEAR REGJLAT(D7 COMMISSION APPROVED BY (NB No. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 NRS.
FORWARD COMMENTS REGARDING BURDEN ESilMATE T0-LICENSEZ EVENT REPORT (LER) Tur tv MMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION O , U.S. NUCLEAR REGULATORY COMMISSION, WASHING A.', DC 20555 0001, AND TO THE PAPERWORK i
RF. DUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCET, WASHINGTON, DC 20503.
FAClllTY NAME (1) DOCKET NUMBER (?) tfR NtMBFR (69 PAGE (3)
YEAR SEQUENTIAL REVISION Prairie Island Unit 1 Nuwere NuMere 93 00 3 OF 3 05000 282 --
12 --
TEXT (If more space is retivired, use additional copies of O C form 366A) (17)
Specifications-required calculations for dose rates and effluent monitor setpoints were not made monthly in accordance with the Offsite Dose ,
Calculations Manual.
During July 1993 effluent releases were normal. Dose and setpoint calculations were performed on the July release data as soon as the oversight was detected. Those calculations verified that the previous monitor setpoints were correct and that the doses to the public were very small at less than 0.2% of quarterly and annual dose limits. Therefore, the nealth and safety of the public were unaffected.
CORRECTIVE ACTION ;
The monthly dose calculations and the monthly effluent monitor setpoint calculations are now being scheduled by the Chemistry Group's work scheduling program, and both calculations have also been added to the Chemistry Group's surveillance program. These processes will schedule the initiation, review and completion of both calculations. Radiation Protection Implementing Procedurec bave been revised to reflect the above changes.
The Radiation Protection and Chemistry Group is reviewing other areas that may depend on non-scheduled actions; any such actions found will be added to the work scheduling programs.
FAILED COMPONENT IDENTIFICATION None. >
PREVIOUS SIMILAR EVENTS Trere have been no previous similar events reported at Prairie Island.
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