ML17263A345

LER 92-006-01:on 920518,main FW Isolations Occurred on SG a Due to Overfeeding SG a While in Manual Control.Caused by Heater Drain Tank Level Control Sys Problem.Administrative Controls Instituted to Ensure Valve Not Open

ML17263A345
Person / Time
Site:	Ginna
Issue date:	07/29/1993
From:	Backus W ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A344	List: ML17263A343 ML17263A345
References
LER-92-006, LER-92-6, NUDOCS 9308090332
Download: ML17263A345 (22)

Text

NRC FORM 366 V.S. NUCLEAR REGULATORY COIBMISSION (64)9) APPAOVED OMB NO. 31504)(04 EXPIRES: 4/30/92 ESTIMATED BUADEN PER RESPONSE TO COMPLY WTH THIS INFOAMA'TION COLLECTION REQVEST: 50.0 HRS. FORWARD LlCENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P630), V.S, NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET,WASHINGTON. DC 20503.

FACILITY NAME (I) DOCKET NUMBER (2I PA E 3 R.E. Ginna Nuclear Power Plant a 5 o a o 2 4 410F11 I

Feedwater Control Perturbations, Due to a Secondary Transient, Causes Steam Generator High Level Feedwater Isolations EVENT DATE (5) LER NUMBER (6I REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

MONTH DAY YEAR YEAR @I( SEQUENTIAL y+iy~ RBV6~ MONTH OAY YEAR FACILITYNAMES DOCKET NUMBERISI NUMBER PFi NUMBER 0 5 0 0 0 0 5 1 8 9 2 9 2 0 0 6 0 1 0 7 2 9 9 3 vill 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF A ((: /Cheek one or more of the foliowinPl l11)

MODE (9) 20.402(B) 20.40S(c) X 73.71(bl 60.73(c)(2)(iv)

POWER 20.405(e)(1)(l) 5026(cl(l ) 50.7 3(c) (2) (v) 73.71(cl LEVEL 0 9 20.405(vill) (ill 50.35(c)12) 50.73(el (21 ( vill OTHER /Specify in AbttieCt below erxf ln Text, h/RC Form 20.405( ~ I(1) Bill 50.73( ~ I (2) I I) 50.73(c l(2) (vill)IA) 34$4/

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LICENSEE CONTACT FOR THIS I.ER (12)

NAME TELEPHONE NUMBER Mesley H. Backus AREA CODE Technical Assistant to the Operations Manager -'

3 1 5 5 2 4 4 4 6 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT l13)

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On May 18, 1992 at approximately 1339 EDST, with the Reactor at approximately 974 full power, Main Feedwater Isolations occurred on the "A" Steam Generator (S/G). These feedwater isolations were caused by overfeeding the "A" S/G while in manual control, following a secondary system pressure transient.

Immediate operator action was to manually control the Main Feedwater Regulating Valves (FRV) to reduce the steam generator water levels and stabilize the plant.

The immediate cause of the event is due to a secondary system pressure transient.

Corrective actions taken or planned are discussed in Section V of the text.

9308090332 930729 PDR (BIDDCK 05000244 8 PDR NRC Form 366 (669)

l NRC FORM 366A US. NUCLEAR REGULATORY COMMISSION (649) APPROVED 0MB NO. 3150dl0i EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLFCTION REQUEST: 50A) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME l'll DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR EAR WR SEQUENTIAL 0/6 IIEVISION

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I ~ PRE EVENT PLANT CONDITIONS The plant was at approximately 974 steady state power with no major activities in progress. Instrument and Control (I&C) Department personnel were investigating the Advanced Digital Feedwater Control System (ADFCS) due to some feedwater oscillations that had occurred at approximately 1110 EDST, May 18, 1992. These feedwater oscillations were being caused by the "A" and "B" Steam Generator (S/G) Main Feedwater Regulating Valves (FRVs) cycling (between 43% and 484), at twice their normal frequency and in opposite phase from each other. This feedwater response (instability while in automatic control) was new and unexpected by the operators.

I1 ~ DESCRIPTION OF EVENT A>> DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES' May 18, 1992, 1337 EDST: A Secondary Side Transient occurs.

o May 18, 1992, 1339 EDST: Event Date and Approximate Time.

0 May 18, 1992, 1339 EDST: Discovery Date and Approximate Time.

0 May 18, 1992, 1342 EDST: Control Room operators restore S/G levels to normal and place Main FRVs in automatic.

NRC FomI 366A (689)

~1 NRC FORM 356A US. NUCLEAR REGULATORY COMMISSION (64)9) APPAOVEO OMB NO. 31500104 EXPIRES'/30)92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50J> HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE AECOADS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP430). U.S. NUCLEAR AEGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504>104>. OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, OC 20503, FACILITY NAME (1I DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)

YEAR SEOVENTIAL ~o): REVISION NVMeER ))BS NUM ER R.E. Ginna Nuclear Power Plant 0 5 0 0 0 2 0 6 0 TEXT Pf mom<<>>o>> b mqu)fed, u>> JSBu>>JHRC FomI 35543) (12)

B~ EVENT:

On May 18, 1992, at approximately 1337 EDST, with the Reactor at approximately 974 full power, a secondary side condensate system decreasing pressure transient occurred. This pressure decrease traveled throughout the entire secondary side and was reflected as low feedwater header pressure and corresponding decrease in differential pressure across both FRVs.

The ADFCS responded to the low feedwater header pressure by increasing the open demand signal to the main FRVs in order to maintain the proper feedwater flow. At,:::Mhi.'s'g~)::;same@~t"ime$ >.:;,":,::.:,:fh'e"';:;,:",:;'.2!C1>:

observing that the main FRVs open demand signals were higher than normal and increasing, and that feedwater flow to the "BL( S/G was higher than appropriate, took manual control of the Main FRVs to prevent further opening of the valves.

Eo'eaai>>'" eiahea'e'"'i.,::aP'z4~ss ii'aa".:)'he Control Room operators manually restored S/G levels to normal, and at approximately 1342 EDST restored the "A" and "B" Main FRVs to automatic control.

N AC Form 3SSA (689)

I NRC FORM 3$ 5A UA. NUCLEAR REGULATORY COMMISSION (689) APPROVED OMB NO. 31504)0e EXPIRES: e/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REQUEST: 50A> HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F430). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) I.ER NUMBER (5) PAGE (3)

YEAR SEQUENTIAL ~lP REVSION NUMSER 4v? NUMIER R.E. Ginna Nuclear Power Plant osooo244 9 2 0 0 6 0 1 0 4pF TEXT /// move e/veoe /e n /vvtved, Ivee ////Ooe ~ NRC Fovm 3/ISAB/ (IT)

CD INOPERABLE STRUCTURESP COMPONENTSP OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

None.

De OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

None.

ED METHOD OF DISCOVERY:

The event was immediately apparent due to alarms and indications in the Control Room.

OPERATOR ACTION:

The Control Room operators took immediate manual actions to control S/G levels and stabilize the plant. Subsequently, the Control Room operators notified higher supervision and the Nuclear Regulatory Commission per 10 CFR 50.72, Non-Emergency, 4 hour Notification.

Ge SAFETY SYSTEM RESPONSES:

The "A" S/G Main FRV began to close automatically as a result of the feedwater isolation signal. Due to the short duration that the signal was present, the valve never fully closed.

IIZ ~ CAUSE OF EVENT Ae IMMEDIATE CAUSE:

The feedwater isolation signal to the "A" S/G Main FRV was due to the "A" S/G narrow range level being

>/= 67%.

NRC Fovm 386A (669)

NRC FORM 366A UN. NUCLEAR REGULATORY COMMISSION

~ (669) APPROVED OMS NO. 3 I500104 EXPIRES: 4/30/92 ESTIMATED SURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REQUEST: 60.0 HRS. FORWARD COMMENTS REGARDINC BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT SRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150@104), OFFICE OF MANACEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) PACE (3)

LER NUMBER (5)

YEAR

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@. SEQUSNTIAI.

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B~ INTERMEDIATE CAUSES:

hi'inui'il"!PRVi","',"'op'e'rati;:o'n","j,;:,::::::;::::,Thi.s situax<<ti.on resulted""'i:n inadvertent overfeeding of also be noted here that just prior to this event, the "A" S/G. It should feedwater automatic control had been experiencing instability with flow oscillations and the operators were sensitive to abnormal indication with ADFCS in automatic control of the FRVs.

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>(hap'O'1'o's NRC Form 366A (689)

I NRC FORM 366A US. NUCLEAR REGULATORY COMMISSION (669) APPROV ED OMB NO. 31500)BE EXPIRES: E/30I92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUEST: 50J) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (PO30), U.S. NUCLEAR AEGULATOAYCOMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (3)50OIOEI. OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, DC 20503.

FACILITY NAME ll) DOCKET NUMBER l2) LER NUMBER (6) PAGE (3)

SEOVENTIAL REVISION YEAR IaI NVMEER NUMBER R.E. Ginna Nuclear Power Plant TEXT llfroorp>>p>>o>> b nqaked, Ir>>>> IEE)oo>>)HRC Forrrr 3()SEBI l)T) osooo244 9 2 0 0 6 0 1 0 6 OF 1 1 IV>> ANALYSIS OF EVENT This event is reportable in accordance with 10CFR50.73, Licensee Event Report system, item (a)(2)(iv), which requires reporting of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)". The feedwater isolation of the "A" S/G was an automatic actuation of an ESF system.

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 the feedwater isolations because:

o The feedwater isolation signals occurred at the required S/G level.

o The plant was quickly stabilized and manual control of FRVs was accomplished to mitigate any consequences of the event.

o As the feedwater isolation signals occurred as designed, the assumptions of the FSAR for steam line break were met.

Based on the above, health it and safety was assured at can be concluded that the all times.

public's V. CORRECTIVE ACTION A>> ACTION,TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS' After S/G levels were stabilized, the Main FRVs were returned to automatic control.

NRC Form 366A (689)

Ly NAC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (689) APPROVED OMS NO.31500104 E XPI A ES: A/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFOAMATION COLLECTION REQUEST: 508) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR AEGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)OI). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (I) OOCKFT NUMBER (2) I.ER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION Q@ NUMSER @g NUMBER R.E. Ginna Nuclear Power Plant o s o o o 2 4 4 9 2 0 0 60 10 7 OF TEXT /// mart t/rtat /t I/Vtrtr/ vtt ~ /R/ant/NRC %%dmI SIJSAB/ (17)

B~ ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

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F tnSILIx,i;tE(near!::,:.,:of('rIE,,ISnaIyj 3:,nip net,:;-::lp h's(e'n':::;:::,::i'iist'input'id'::,';,:.:,:ta"'.:,.'-;':,;'en'~'ur'e':,,'",:,,th After reviewing the results of troubleshooting and discussions with Westinghouse, the following is an outline of the corrective actions being taken or planned in response to the feedwater control instability problems (and ADFCS transient response for secondary system transient):

0 Short Term Response:

a) I&C technicians loosened and lubricated the actuator to stem connection block for the "8" FRV.

b) Operations was directed to place the Main FRV bypass valves in full open position and in automatic control, to reduce the feedwater control instability problem.

c) The packing on both FRVs was relaxed to minimum torque, to reduce any potential friction of the valve stem.

0 Intermediate Term Response:

a) Westinghouse has evaluated ADFCS "tuning constants" and has supplied new ADFCS gain values, in an attempt to reduce the ADFCS impact on feedwater control instability problems.

b) The new ADFCS gain values have been installed in the ADFCS software.

Instability problems have not been eliminated as a result of these new gain values.

NRC Form 366A (689)

NRC FORM 366A UN. NUCLEAR REGULATORY COMMISSION (689) APPROVED OMS NO. 31500104 EXPIRES 4/30N2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F830), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET,WASHINGTON. OC 20503.

FACILITY NAME (II DOCKET NUMBER (2) LEA NUMBER (6) PAGE (3)

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0 Long Term Response:

a) Valve characteristic data (with and without valve shaft packing in place) will be reviewed.

Stat;us.'.F':-",":.-;compl'etc b) The vendors of the Main FRV actuator and positioner will be consulted, requesting their recommendations for valve packing and positioner operation, based on a more detailed review of the diagnostic testing.

c) The calibration procedures for the Main FRVs will be revised to include valve response characteristics during scheduled calibrations.

B'C%tns;::,;:~X'-".:;!FL':, coe'ss d) N'gaO6'eX:kiig:-:::+OX'k';:hejueStjQ~. (EWR) 4773 will apply the informati.on obtained from other actions, and is intended to enhance feedwater control and response to plant transients. It improvements will be obtained in both is envisioned that electronic and pneumatic performance, as a result of these enhancements.

8~4tiis,:.::,:;,.:::;;Complete NAC Form 366A (689)

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FACILITY NAME (I) DOCKET NUMBER (2) PAGE (3)

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NRC Form 388A (669)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVEO OMB NO. 31500104 EXPIRES( 4130(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT {LER) INFORMATION COLLECTION REQUEST: 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31600104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

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VZ ~ ADDITIONAL ZNFORMATION Ae FAILED COMPONENTS:

None.

B~ PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: LER 91-009 was a similar event with a different root cause.

C~ SPECIAL COMMENTS:

None.

NRC FomI 368A (669)

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