ML17309A654

LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr

ML17309A654
Person / Time
Site:	Ginna
Issue date:	05/27/1999
From:	Mecredy R, St Martin J ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-99-008, LER-99-8, NUDOCS 9906040057
Download: ML17309A654 (11)

Text

e CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)

ACCESSION NBR 9 9 0 6 04 0 0 57

~ DOC DATE ~ 9 9 /0 5/2 7

~ NOTARIZED e NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION ST MARTIN,J.T. Rochester Gas 6 Electric Corp.

MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECXPIENT AFFXLXATION VXSSZNG,G.S.

SUBJECT:

LER 99-008-00:on 990427,overtemperature delta T reactor trip occurred due to faulted bistable during calibr of redundant channel. Plant was stabilized in mode 3 6 faulted bistable was subsequently replaced. With 990527 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 0

,RECIPIENT COPXES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VISSXNG,G. 1 1 INTERNAL: AEOD/SPD/RRAB 1 1 LE CE ER 1 1' NRR/DZPM/ZOLB 1 1 NRR/DIPM IQMB 1 NRR/DRIP/REXB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EXB 1 . 1 RGNl FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 D

NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 Was%

~~~ Q+w c V M g-L F-<~ E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LISTS THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

AND SP IKKHESTER G4S

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AREA CODE Ild 54b P00 ROBERT C. MECREOY Yge tis4Wnt Nuclsoi Opsiuhoni May 27, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

LER 1999-008, Faulted Bistable During Calibration of Redundant Channel Results in Overtemperature Delta T Reactor Trip R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

The attached Licensee Event Report LER 1999-008 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "Any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS) ".

Ve ruly you s, Robert C. Mecr y xc: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Adm'nistrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 194O6 Q3 OD@

U.S. NRC Ginna Senior Resident Inspector 9906040057 990527 PDR hDOCK 05000244 8 PDR

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NRC llM 3SSA U.S. NUCLEAR REOULATORY COMMISSIN hi l cia LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION

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. FAClLITY NAME ttl DOCKET l2) LER NUMBER lel PAGE l3l st SJlii! ill HWNh hVShih R.E. Ginna Nuclear Power Plant 05000244 1999 008 00 g OF TEXT //f more sproe rs required. use edChrrone/ oopres of N/r C Form 366'A/ 1171 PRE EVENT PLANT CONDITIONS:

On April 27. 1999, the plant was in Mode 1 at approximately 90')I reactor power. A power escalation was in progress as the plant started up from the 1999 refueling outage. Instrument and Control llhC) technicians were in the process of several calibrations and tests in channel 2 of the reactor protection system IRPS), and had defeated various RPS outputs from channel 2. Among procedures being used were CPI.TRIP-TEST 5.20, CPI AXIAL.N.42, CPI PRESS.946, and CPI PRESS 949. Channel defeat involves placing numerous bistables into the topped condition in protection racks in the Control Room. and results in a similar number of Main Control Board IMCBI annunciator alarms.

Unrelated to these calibrations, the "8" main teedwater regulating valve IMFWRV) was in "manual valve position control due to concerns with automatic control of this valve.

DESCRIPTION OF EVENT:

A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:

o April 27, 1999, 1248 EDST: Event date and time.

o April 27, 1999, 1248 EDST: Discovery date and time.

o April 27. 1999, 1248 EDST: Control Room operators verify both reactor trip breakers open and verify all control and shutdown rods inserted.

o . April 27, 1999, 1255 EDST: Control Room operators manually close both main steam isolation valves to limit a reactor coolant system cooldown.

o April 27, 1999, 1258 EDST: Control Room operators ensure both main feedwater pumps are secured to limit a reactor coolant system cooldown.

April 27, 1999. 1325 EDST: Plant is stabilized in Mode 3.

8. EVENT:

On April 27, 1999, the plant was in Mode at approximately 9096 reactor power. A power 1

escalation was in progress as the plant started up from the 1999 refueling outage. Instrument and Control (lhC) technicians were in the process of several calibrations and tests in channel 2 "of the reactor protection system (RPS), and had defeated various RPS outputs from channel 2. Among procedur<.s being used were CPI TRIP. TEST-5.20, CPI.AXIAL.N.42, CPI.PRESS.946, and CPI ~

PRESS.949. Channel defeat involves placing numerous bistables into the tripped condition in protection racks in the Control Room. and results in a similar number of Main Control Board IMCB) annunc:ator alarms.

Unrelated to these calibrations. the "8" main feedwater regulating valve IMFWRV) was in "manual" valve position control due to concerns with automatic control of this valve.

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NC lddA U.S. MUCLEAR REOULATORY COSNNISSION a isla LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION

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FACKSTY NASSE l1l OOCrtET I2) LER HuhsaER ldl PAOE <3)

QtSlhfNl INWth R.E. Ginna Nuclear Power Plant 05000244 999 ~ 008 00 1

d OF TEXT rrl more epece ie reqiered. use eddrrxwer copse! or HRC form 366AJ l17I Based on the above and a review of post trip data and pest plant transients, it can be co luded that the plant operated as designed, that there were no unreviewed safety questions. and that the pubhc's health and salety was assured a'I all 'times.

V. CORRECTIVE ACTION:

A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE EVENT NORMAL STATUS:

The "A SG was restored to operable status when SG level in the A" SG increased above 18%

level. by addition of AFW. Subsequently, levels were restored to their normal operating levels.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE Dunng subsequent bench testing ot the faulted bistable, erratic behavior was observed. The bistable will be sent to NUS Scientech Inc. for further analysis.

Vl. ADDITIONALINFORMATION:

A. FAILED COMPONENTS:

The faulted component was a bistable module. manufactured by NUS Scientech Inc., Model DAM 503 01 differential bistable. This bistable was installed as TC 407CID in the Overtemperature Delta T function in December 1997, and had performed acceptably in service until this event.

B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event histoncal 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.

Recent reactor trips w<<h different root causes include LERs 98 002, 98 012, and 1999 007.

C. SPECIAL COMMENTS:

None