ML17263A542

LER 94-001-00:on 940119,Radition Monitor R-32 Declared Inoperable Due to Low Output by One Decade.Correct Value of Calibr Constant for R-32 Determined & Edited Into R-32 Control terminal.W/940217 Ltr

ML17263A542
Person / Time
Site:	Ginna
Issue date:	02/17/1994
From:	Mecredy R, St John J ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-001, LER-94-1, NUDOCS 9403010270
Download: ML17263A542 (13)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9403010270 DOC.DATE:,94/02/17 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION ST JOHN,J.T. Rochester Gas & Electric Corp.

MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 94-001-00:on 940119,Radition Monitor R-32 declared inoperable due to low output by one decade. Correct value of D calo.br constant for R-32 determined & edited into R-32 control terminal.W/940217 ltr. S DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR J ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

i SIZE: C7 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 D

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: AEOD/DOA 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 NRR/DE/EELB 1 1-NRR/DE/EMEB 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 DSSA. SPLB 1 1 NRR/DSSA/SRXB 1 REG ILE 02 1 1 RES/DS IR/EIB 1 RGB=FILE 01 1 1 EXTERNAL EG &G BRYCE ~ J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT .1 1 R

D A

D D

NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

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

Seen Srnrt ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N. Y. 14649.0001 ROBERT C MECREDY, TELEPHONE Vice Presidenl AREA CODET16 546 2700 Olnne Nuclear Production February 17, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

LER 94-001, Radiation Monitor R-32 ("B" Main Steam Line)

Inoperable, Due to Personnel Error, Causes a Condition Prohibited by Plant Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), which requires a report of, "Any operation or condition prohibited by the plant's Technical Specifications", the attached Licensee Event Report LER 94-001 is hereby submitted.

This event has in no way affected the public's health and safety.

Very truly yours, C~

Robert C. Mecredy xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9403010270 940217 PDR ADOCK 05000244 S PDR

NRC FORH 366 U.S NUCLEAR REGULATORY COINIISSION APPROVED BY (NNI NO. 3150-0104 (5-92) ~ ~

EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY IIITH THIS INFORHATION COLLECTIOH REQUEST: 50,0 HRS.

LICENSEE EVENT REPORT (LER) FORNARD COHMEHTS REGARDING BURDEN ESTIHATE TO THE IHFORHATIOM AND RECORDS MANAGEMENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSIOM, (See reverse for required nurher of digits/characters for each block) NASHIHGTON, DC 20555-0001, AMD 'TO THE PAPERMORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHENT AND BUDGET UASHINGTON DC 20503.

FAGILITY eua <<1) R.E. Ginna Nuclear Power Plant DOCKET NINBER (2) PAGE (3) 05000244 10F9 TITLE (4) Radiation Honitor R-32 ("B" Hain Steam Line) Inoperable, Due to Personnel Error, Causes a Condition Prohibited by Plant Technical Specifications EVENT DATE 5 I.ER NWSER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 SEQUENTIAL REVI SION FACILITY NAHE DOCKET NUMBER HONTH DAY TEAR YEAR HOHTH DAY TEAR HUHBER HUHBER 01 19 94 94 --001-- , 00 02 17 94 FACILITY HAHE DOCKET NUHBER OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR: Check one or more 11 H(nE (9) N 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POUER 097 20.405(a )(l)(i) 50.36(c)(l) 50.73(a)(2)(v) 73.71(c)

LEVEL <<10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50 73(a)(2)('I) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20 '05(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A LICENSEE CONTACT FOR THIS LER 12 HAME John T. St. Hartin - Director, Operating Experience TELEPHONE NUHBER (Include Area Code)

(315) 524.4446 COMPLETE ONE LINE FOR EACH CQIPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE REPORTABLE CAUSE SYSTEH COMPOHEHT HAHUFACTURER CAUSE SYSTEH COHPOMENT HAMUFACTURER TO NPRDS TO HPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES SUBHI SSI ON (If yes, complete EXPECTED SUBHISSIOM DATE). X NO DATE (15)

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

On January 19, 1994, at approximately 1330 EST, with the reactor at approximately 97go steady state power, the output of the "B" Main Steam Line Radiation Monitor R-32 was discovered to be low by one decade. R-32 was declared inoperable.

Investigation revealed that a calibration constant was incorrectly documented due to a transposition error, and the'incorrect value was edited into the R-32 control terminal. Immediate corrective action was to edit the correct value of the calibration constant into R-32. This restored the output of R-32 to the correct range, and R-32 was declared operable. (This event is NUREG-1022 (A) cause code.)

Corrective action to preclude repetition is outlined in Section V (B).

This LER meets the requirements of a Special Report required by the Ginna Technical Specifications.

NRC FORM 366 (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COIIISSION APPROVED BY QGI NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY llITH THIS INFORMATION COLLECTIOM REQUEST: 50.0 HRS.,

FORNARD COMMENTS REGARDIHG,BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE IHFORNATIOH AMD RECORDS NAMAGEHENT BRANCH TEXT CONTINUATION (NNBB 7714), U.S. NUCLEAR REGULATORY CONNISSIOM, llASHIHGTOM, DC 20555-0001 AND TO THE PAPERNORK REDUCTIOH PROJECT (31(0.0104), OFFICE OF MANAGEMENT AND BUDGET .NASHINGTON DC 20503.

FACILITY MANE 1 DOCKET NINBER 2 LER HLNSER 6 PAGE 3 SEQUENTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 2 OF 9 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

I. PRE-EVENT PLANT CONDITIONS The reactor was at approximately 97> steady state reactor power. An engineer was reviewing a printout from the control terminal for the UBU Main Steam Line Radiation Monitor (R-32). This review was being done as part of research for a planned modification. The scope of the modification is to replace the standby recorder for main steam

. line radiation levels (recorder RK-47A) with continuous indication of these radiation levels in the Control Room.

II. DESCRIPTION OF EVENT A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:

o October 7, 1993:, R-32 calibrated per CPI-MON-R31/R32. The value of the calibration constant is incorrectly transposed and edited into the R-32 control terminal. (Event date) o October 7, 1993: Procedure PT-17.5 changed to reflect the tolerance band of output readings for R-32, based on the calibration constant edited into the R-32 terminal. PT-17.5 performed to verify operability of R-'32.

o January 19, 1994, 1330 EST: Discovery date and time.

o January 19, 1994, 1547 EST: The correct value of the calibration constant for R-32 is determined and edited into the R-32 control terminal, per CPI-MON-R31/R32. R-32 restored to operable status.

HRC FORM 366A (5.92)

NRC FORH 366A U.S NUCLEAR REGULATORY CQtllSSION APPROVED BY (RN NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COHMENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGEHENT BRANCH TEXT CONTINUATION (HNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION/

WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3130-0104), OFFICE OF HANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME 1 DOCKET NEER 2 LER N NBER 6 PAGE 3 YEAR SEQUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 3 OF 9 TEXT (If more space is required, use additionaL copies of NRC Form 366A) (17)

B. EVENT P

The annual calibration of the "B" Main Steam Line Radiation Monitor (R-32) was completed on October 7, 1993, in accordance with calibration procedure CPI-MON-R31/R32, "Calibration of DAM-3 Steam Line Radiation Monitors R31 and R32". As part of the calibration, the Instrument and Control (I&C) -technician calculates a calibration constant, based on actual detector sensitivity and source strength. After completion of the calibration, the technician then edits the new value into the control terminal (SPING CT-1) for R-32 (unit 04, channel 02 of the SPING CT-1). (The'SPING CT-1 controls various radiation monitor channels throughout the plant.) The calibration constant is an "editable parameter", and is used to convert counts per minute (CPM) from the detector into readings of millirem per hour (mr/hr). When the reading reaches 0.1 mr/hr, recorder RK-47A in the Control Room is activated, and begins recording.

When the calibration constant was calculated (on October 7, 1993), the I&C technician misplaced the decimal point while transposing the calculated value from decimal notation to scien-tific notation., Consequently, an incorrect power of ten (one decade too low) was recorded on the procedure data sheet and edited into the R-32 control terminal. (The decimal reading was correctly calculated as "0.0197", but was incorrectly transposed and documented as 1.97 E-03 instead of 1.97 E-02.) '. The parameter was then edited into the R-32 control ter'minal as 1.97 E-03.

I Surveillance procedure PT-17.5-, "High Range Effluent Monitors R-12A, R-14A, R-15A, R-31, R-32", was then changed by the I&C technician, on October 7, 1993, to reflect the tol'erance band of output readings for R-32, based on the new value of the calibration constant. PT-17.5 was performed, and the Plant Process Computer System (PPCS) was checked to confirm that the ou'tput of R-32 was within the PPCS "quality code" and "current value" tolerances. R-32 was then declared operable by the Control Room operators.

NRC FORH 366A (5-92)

HRC FORM 366A U S NUCLEAR REGULATORY CQIIISSIOH APPROVED BY OIB NO. 3150-0104 (5 92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPOHSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEHEHT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSIOHi WASHINGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3140 0104), OFFICE OF MANAGEMENT AHD BUDGET WASHINGTON DC 20503.

FACILITY NAKE 1 DOCKET NNBER 2 LER NNBER 6 PAGE 3 SEQUENT I AL REVI SION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 4 OF 9 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

PT-17.5 was performed each month thereafter to verify the operabili;ty of R-32. Daily channel checks were performed by Control Room operators to confirm*the PPCS values were still "

within tolerances.

On January 19, 1994, at approximately 1330 EST, with the reactor at approximately 974 steady state reactor power, an engineer was reviewing a printout from the CT-1 control terminal. This review was being done as part of research for a planned modification. The scope of the modification is to replace standby recorder RK-47A with continuous indication of main steam line radiation levels in the Control Room. The engineer calcu-lated the calibration constants, and, based on his knowledge of the system, observed that the constant being used in R-32 was not within allowable system parameters. Further investigation revealed that this inconsistent value was caused by. the transposition error discussed above.

?

The engineer notified the I&C group of his discovery. I&C concurred with the engineer. They notify':ed the Control Room operators that R-32 had'an incorrect calibration constant and that the output was one decade too low.

The Control Room operators evaluated this information, and formally declared R-32 inoperable at approximately 1430 EST on January 19, 1993. The correct value of the calibration constant was edited into the R-32 control terminal, per CPI-MON-R31/R32.

PT-17.5. was changed to reflect the data for the corrected value of the calibration constant and was performed to verify the operability of R-32. The Control Room operators checked the PPCS, and confirmed that the output was within the PPCS tolerances.'-32 was declared operable, and returned to service at approximately 1547 EST, January 19, 1994.

C. I NOPERABLE STRUCTURES i COMPONENTS I OR SYSTEMS THAT CONTRI BUTED TO THE EVENT:

None D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

None NRC FORM 366A (5-92)

NRC FORH 366A U S. NUCLEAR REGULATORY COHIISSION APPROVED BY QlB NO 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY UITH THIS INFORNATION COLLECTIOH REOUEST: 50.0 HRS.

FORIIARD COHHEHTS REGARDIHG BURDEN ESTINATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS NANAGEHENT BRANCH TEXT CONTINUATION (NHBB 7714), U.S. NUCLEAR REGULATORY CONHISSION, MASHIHGTOH, DC 20555-0001 AHD TO THE PAPERIQRK REDUCTION PROJECT (3110-0104), OFFICE OF NANAGEHEHT AND BUDGET NASHINGTOH DC 20503.

FACILITY NAHE 1 DOCKET NNBER 2 LER NINBER 6 PAGE 3 YEAR SEOUENT IAL REVISION R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 5 OF 9 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

E. METHOD OF DISCOVERY:

This event was identified by an engineer, who reviewed a printout from the CT-1 control terminal as part of research for a planned modification to replace standby recorder RK-47A with continuous indication in the Control Room. The engineer observed that the calibration constant being used was not within allowable system parameters.

F. OPERATOR ACTION:

Control Room operators were notified of this event, and

'

The declared R-32 inoperable., Subsequently, the Control Room operators notified higher supervision and the NRC. R-32 was declared operable after the correct calibration constant was edited into the R-32 control terminal, PT-17.5 was, satisfactorily completed, and PPCS channel checks of R-32 were performed.

G. SAFETY SYSTEM RESPONSE:

None III. CAUSE OF EVENT A. IMMEDIATE CAUSE:

The immediate cause of R-32 being considered to be inoperable was that the output of R-32 was discovered to be low by one decade, such that R-32 would have activated the RK-47A recorder at approximately 1 mr/hr instead of the design value of 0.1 mr/hr.

B. INTERMEDIATE CAUSE:,

The intermediate cause of the low output of R-32 was that the value of the calibration constant was transposed incorrectly when changing the value from decimal notation to scientific notation.

HRC FORH 366A (5-92)

NRC FORN 366A U.S. NUCLEAR REGULATORY CIBIISSION APPROVED BY QGI NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTINATED BURDEN PER RESPONSE TO COHPLY NITH THIS INFORNATION COLLECTION REQUEST: 50.0 HRS.

FORNARD COHNEHTS REGARDING BURDEN ESTINATE TO LICENSEE EVENT REPORT (LER) THE IHFORHATIOH AND RECORDS NANAGENENT BRAHCH TEXT CONTINUATION (HNBB 7714), U.S. NUCLEAR REGULATORY CONHISSIOH ~

NASNINGTOH, DC 20555 0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF NANAGEMEHT AND BUDGET NASHINGTON DC 20503.

FACILITY NANE 1 DOCKET NIMBER 2 LER NINBER 6 PAGE 3 SEQUEHTIAL RE VIS IOH YEAR R.E. Ginna Nuclear Power Plant 05000244 M

6OF9i 94 -- 001-- 00 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

C. ROOT CAUSE:

The underlying cause of the transposition error was a personnel error by an I&C technician. This was a cognitive personnel error and was not contrary to the calibration procedure being .

used. There were no unusual characteristics of the work location which contributed to the error. (This event is NUREG-1022 (A) cause code, Personnel Error.)

IV. ANALYSIS OF EVENT:

This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), which requires a report of, "Any operation or condition prohibited by the plant's Technical Specifications". The output of R-32 being one decade too low

.resulted in R-32 being considered inoperable. Since this condition existed since October 7, 1993, and was not discovered until January 19, 1994, R-32 was inoperable for more than seven .days. This is a condition prohibited by the Ginna Technical Specifications (TS).

o Specification 3.5.4 states:

The radiation accident monitoring instrumentation channels shown in Table 3.5-6 shall be operable,-.whenever the reactor is at or above'ot shutdown. With one or" more radiation monitoring channels inoperable, take the action shown in Table 3.5-6.

Startup may commence or continue consistent with the action statement.

o Action statements from Table 3.5-6 states:

With the number of operable channels less than required by the Minimum Channels Operable requirements, either restore the inoperable channel(s) to operable status within 7 days of the event, or prepare,and submit a Special Report to the Commission within 30 days following the event. outlining the action'.taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

HRC FORN 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COWISSION APPROVED BY QNI NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY NITH THIS IHFORHATIOH COLLECT IOH REQUEST: 50.0 HRS.

FORNARD CONHEHTS REGARD IHG BURDEN EST IHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATIOH AND RECORDS HAHAGEHEHT BRANCH TEXT CONTINUATION (HHBB 7714), U.S. NUCLEAR REGULATORY CONHISSIOH, NASHIHGTON, DC 20555-0001, AND TO THE PAPERNORK REDUCTION PROJECT (3150-0104), OFFICE OF HAHAGENENT AND BUDGET NASHINGTON DC 20503.

FACILITY NAHE 1 DOCKET NINIBER 2 LER NINBER 6 PAGE 3 SEQUENTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 7 OF 9 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

The "B<< Main Steam Line Radiation Monitor (R-32) inoperability was not discovered until January 19, 1994. Therefore, the condition was not recognized at the time a Special Report would have been required. Consequently, a Special Report was not submitted within 30 days following the event on October 7, 1993.

An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:

There were no operational or safety consequences or implications attributed to R-32 being inoperable for greater than seven days, because R-32 was still functioning and capable of responding to radiation levels at 104 of the TS limits, instead of the desired 14 of TS limits. Because the setpoint is very conservative to begin with, the one decade error in the calibration constant still allowed the system to respond well within the TS limits.

The design for R-32 is that when the output reaches 0.1 mr/hr, recorder RK-47A activates to provide indication and recording of R-32 in the Control Room. R-32 was.functioning correctly, but due to this transposition error, the output was in error low by one decade. (The detector for R-32 continued to function as designed, and continued to detect and monitor radioactivity. The detector still, output, as measured in CPM was wa's correct. However, the. output one'ecade too low.)

reading," as 'expressed in mr/hr, Therefore, the RK-47A recorder in the Control Room would not have activated until the actual radiation reached 1 mr/hr (one decade higher than desired). This corresponds to a release concentration of approximately 1 E-02 microcuries per cubic centimeter (uCi/cc) noble gases or a release rate of approximately 1.33 E-02 curies per

'econd (Ci/sec). Note that the "instantaneous" TS limit for a release rate from the location would be similar to the Air Ejector or 1.42 E-01 Ci/sec. The error before the recorder started would represent 104 of the TS limit, rather than 1% when the correct calibration constant is used.

NRC FORI4 366A (5.92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COIIISSION 'PPROVED BY (NB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO CONPLY IJITH THIS INFORHATIOH COLLECTIOH REQUEST: 50.0 HRS.

FORIIARD COHHEHTS REGARDIHG BURDEN ESTINATE TO LICENSEE EVENT REPORT (LER) THE IHFORHATION AHD RECORDS NANAGEHENT BRANCH TEXT CONTINUATION (NHBB 7714), U.S. NUCLEAR REGULATORY CONHISSIOH, IIASHIHGTON, DC 20555-0001 AND TO THE PAPERNORK REDUCTION PROJECT (3140-0104), OFFICE OF HANAGEHENT AND BUDGET IIASHINGTON DC 20503.

FACILITY lONE 1 DOCKET NINBER 2 LER NINBER 6 PAGE 3 YEAR SEQUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 94 -- 001 00 8 OF 9 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

The release path that R-32 monitors is main steam relief valve discharge. R-32 readings are used to determine the potential dose to the general population through releases from the steam generators, when the relief valves have lifted after a primary to secondary steam generator leak. There were no releases through this release path during the time that R-32 was considered inoperable. If relief valves had lifted during this time, the duration of the release and the amount of activity released would have been determined from data from several sources, including R-32. R-32 data 'would have been discovered to be inconsistent with other data't such a time, and would not affect the accuracy of release calculations.

Based on the above, and safety was assured at all times.

it can be concluded that the public's health V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o The correct value of the calibration constant for R-32 was determined and edited into the R-32 control terminal, per CPI-MON-R31/R32.

o PT-17.5 was changed to reflect the correct value of the calibration constant and was performed to verify operability of R-32.

o A PPCS channel check was performed to verify operability of R-32.

C o The other radiation channels controlled by the SPING CT-1 control terminal were verified to have the correct calibration constants edited into the control terminal.

HRC FORH 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGUULTORY CQBIISS ION APPROVED BY QGI NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO CONPLY IIITH THIS IHFORHATION COLLECTION REQUEST: 50.0 HRS ~

FORIIARD COHHEHTS REGARDIHG BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGENENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSIOH ~

TEXT CONTINUATION llASHINGTOH, DC 20555-0001 AND TO THE PAPERNORK REDUCTION PROJECT (3140-0104), OFFICE OF HANAGEHEHT AHD BUDGET MASHING'TOH DC 20503.

FACILITY NAHE 1 DOCKET NNBER 2 LER NINBER 6 ~ PAGE 3 SEQUENT IAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 94 -- 001-- 00 9 OF 9 TEXT (lf more space is required, use additional copies oi HRC Form 366A) (17)

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE-o Procedure CPI-MON-R31/R32 has been revised to provide a tolerance band for acceptable values of the calibration constant. This tolerance will be expressed in both decimal and scientific notation.

o Calibration procedures for other channels controlled by CT-1 have been reviewed. Procedures will be revised to provide the appropriate tolerance bands for editable parameters.

o The importance of making calculations correctly will be reemphasized to all I&C personnel, including the consequences of incorrect results.

VI. ADDITIONAL INFORMATION:

A. FAILED COMPONENTS:

None B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Nuclear Power Plant could be identified.

C. SPECIAL COMMENTS:

None NRC FORH 366A (5-92)

l I