ML17264A126

LER 95-006-00:on 950630,34.5 Kv Offsite Power Circuit 751 Was Lost Due to Offsite Lightning Strike & Resulted in Automatic Start of a Edg.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1 to Stabilize Plant

ML17264A126
Person / Time
Site:	Ginna
Issue date:	07/31/1995
From:	St Martin J ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A125	List: ML17264A124 ML17264A126
References
LER-95-006, LER-95-6, NUDOCS 9508090112
Download: ML17264A126 (8)

Text

NRC FORM 366 U.S. NUCLEAR REGULATORY COMHISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

LICENSEE EVENT REPORT (LER) FORllARD COHMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMHISSION, (See reverse for required number of digits/characters for each block) WASHINGTON, OC 20555-0001 AND TO THE PAPERNORK REDUCTION PROJECI'3150.0104), OFFICE OF MANAGEMENT AND BUDGET MASHINGTON DC 20503.

FAcILITY NAHE (1) R. E ~ Ginna Nuclear Power Plant DOCKET NUHBER (2) PAGE (3) 05000244 10F8 TITLE (4) Loss of 34.5 KV Offsite Power Circuit 751, Oue to Offsite Lightning Strike, Results in Automatic Start of >>A>>

Emergency Diesel Generator EVENT DATE (5) LER NUHBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

SEQUENTIAL REVISION FACILITY NAME DOCKET NUHBER MONI'H DAY YEAR YEAR HONTH DAY YEAR NUHBER NUMBER 06 30 95 95 --006-- 00 07 31 95 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHE:ITS OF 10 CFR rit (Check one or more) (11)

(9) N 20.402(b)

MODE 20.405(c) 50.73(a)(2)(iv) 73.71(b)

PONER 20.405(a ) (1) ( i ) 50.36(c>(1) 50.73(s)(2)(v) 73.71(c) 097 LEVEL (10) 20.405(a) (1) ( i i ) 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)(ri) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20.405(a>(1)(v) 50.73(a)(2)(iii) 50.73(a)(2>(x) NRC Form 366A)

LICENSEE COHTACT FOR THIS LER (12)

NAHE John T. St. Hartin - Technical Assistant TELEPHONE NUMBER (Include Ares Code)

(716) 771-3641 COMPLETE ONE LINE FOR EACH COHPONEHT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COHPONENT REPORTABLE REPORTABLE MANUFACTURER CAUSE SYSTEH COMPOHENT MANUFACTURER TO NPRDS TO NPRDS

~

EA CBL5 XOOO SUPPLEHEHTAL REPORT EXPECTED (14) EXPEC'TED MONTH DAY YEAR YES SUBHISSION (If yes, corrplete EXPECTED SUBHISSION DA'IE). X NO DATE (15>

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

On June 30, 1995, at approximately 1528 EDST, with the reactor at approximately 97% steady state power, power from Circuit 751 (34.5 KV offsite power source) was lost, due to a lightning strike on an offsite utility pole for Circuit 751. This resulted in deenergization of 4160 Volt bus 12A and "A" train 480 Volt safeguards buses 14 and 18. The "A" Emergency Diesel Generator (D/G) automatically started and reenergized buses 14 and 18 as per design. There was no change in reactor power or turbine load.

Immediate corrective action was to perform the appropriate actions of Abnormal Procedure AP-ELEC.1 (Loss of 12A And/Or 12B Busses) to stabilize the plant and to verify that the "A" Emergency D/G had started and reenergized buses 14 and 18.

This event is NUREG-1022 Cause Code (C).

Corrective action to prevent recurrence is outlined in Section V.B.

NRC FORM 366 (5 92) 9508090ii2 950731 PDR ADQCK 05000244 S PDR

NRC FORM 366A U.S ~ NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150 0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MITH THIS INFORHATION COLLECTIOH REQUEST: 50.0 HRS.

FORNARD COMMENTS REGARDIHG BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY C(XQISSION, IIASHIHGTON, DC 20555-0001 AND TO THE PAPERNORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AHD BUDGET NASHINGTOH DC 20503.

FACILITY NAHE (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL RE VIS IOH YEAR RE ED Ginna Nuclear Power Plant 05000244 NUMBER NUMBER 20F8 95 -- 006-- 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

I. PRE-EVENT PLANT CONDITIONS The plant was at approximately 97% steady state reactor power with no major operational activities in progress. A thunderstorm was in progress in the vicinity of the plant.

The offsite power configuration to the plant was in the normal "50% /

50%" offsite power lineup:

Circuit "A" 751 (34.5 KV offsite power source) was supplying power to the train 480 Volt safeguards buses 14 and 18 through 34.5 KV to 4160 Volt transformer 12A (12A transformer) to 4160 Volt bus 12A, and through the safeguards bus 4160 Volt to 480 Volt transformers.

Circuit "B" 767 (34.5 KV offsite power source) was supplying power to the train 480 Volt safeguards buses 16 and 17 through 34.5 KV to 4160 Volt transformer 12B (12B transformer) to 4160 Volt bus 12B, and through the safeguards bus 4160 Volt to 480 Volt transformers.

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

o June 30, 1995, 1528 EDST: Event date and time.

o June 30, 1995, 1528 EDST: Discovery date and time.

June 30, 1995, 1528 EDST: Control Room operators verify the "A" Emergency Diesel Generator (D/G) operation and that safeguards buses 14 and 18 and Instrument Bus "B" are energized.

June 30, 1995, 1702 EDST: Safeguards buses 14 and 18 were transferred to Circuit 767 from the "A" Emergency D/G.

June 30, 1995, 1708 EDST: The "A" Emergency D/G was stopped and realigned for auto standby.

June 30, 1995, 1814 EDST: Circuit 751 declared operable.

o July 2, 1995, 2343 EDST: Offsite power configuration was restored to the normal n50% / 50%" lineup.

HRC FORM 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISS ION APPROVED BY OHB NO. 3150-0104 (5.92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COHHENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE IHFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COMHISSION, TEXT CONTINUATION WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150 0104), OFFICE OF MANAGEHENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUHBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVISIOH YEAR R.E. Ginna Nuclear Power Plant 05000244 NUHBER NUHBER 95 -- 006-- 00 3 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

B. EVENT:

On June 30, 1995, at approximately 1528 EDST, with the reactor at approximately 97% steady state full power, the Control Room received numerous annunciator alarms, including Annunciator E-14 (LOSS B INSTR. BUS). The Control Room operators determined that Circuit 751 (34.5 KV offsite power source) was deenergized, and that "A" train 480 Volt safeguards buses 14 and 18 had lost their power supply from 4160 Volt bus 12A. The "A" Emergency D/G had automatically started and was tied to safeguards buses 14 and 18.

Buses 14 and 18 had been momentarily deenergized and 120 Volt AC Instrument Bus "B" (powered from bus 14) had also been momentarily deenergized.

The Control Room operators verified that reactor coolant system temperature and pressure were stable, and that there was no change in reactor power or turbine load. They performed the appropriate actions of Abnormal Procedure AP-ELEC.1 (Loss of 12A And/Or 12B Busses) to stabilize the plant. They verified that the "A" Emergency D/G was operating properly and that safeguards buses 14 and 18 and Instrument Bus "B" were energized. The Control Room operators observed that Circuit 751 and bus 12A displayed zero (0) voltage. The loss of power from Circuit 751 resulted in undervoltage on safeguards buses 14 and 18, and the "A" Emergency D/G automatically started within ten (10) seconds as per design and reenergized these buses. When bus 14 was reenergized, Instrument Bus "B" was also automatically reenergized.

Energy Operations personnel were notified concerning the loss of Circuit 751. Personnel from the "Engineering, Operations, and Gas Services" department investigated field conditions and determined that a lightning strike caused the loss of power from Circuit 751, and determined the location of the lightning strike.

The Control Room operators referred to Equipment Restoration procedure ER-ELEC.l (Restoration of Offsite Power) to restore offsite power to 4160 Volt bus 12A and 480 Volt safeguards buses 14 and 18. The Control Room operators closed 4160 Volt circuit breaker 52/12BY to energize bus 12A from Circuit 767, via the 12B transformer, at approximately 1557 EDST. At approximately 1702 EDST, safeguards buses 14 and 18 were transferred to Circuit 767 from the "A" Emergency D/G. (Circuit 767 had remained in operation, supplying "B" train 480 Volt safeguards buses 16 and 17 throughout the event.)

NRC FORH 366A (5 92)

HRC FORH 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS.

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

FACILITY NAME (1) DOCKEl'UHBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 NUHBER NUMBER 4OF8 95 -- 006-- 00 TEXT (If more space is required, use additionaI copies of NRC Form 366A) (17)

At approximately 1708 EDST, June 30, 1995, the "A" Emergency D/G was stopped and realigned for auto standby. Circuit 751 was declared operable at approximately 1814 EDST, but was maintained as the plant's backup supply of offsite power rather than realigning the electrical system during continuing thunderstorm conditions.

C INOPERABLE STRUCTURES I COMPONENTS r OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

None D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

The momentary loss of power to buses 14 and 18 (at 1528 EDST) caused the trip of the common sample pump for radioactive effluent monitoring of plant ventilation by channels R-10B (iodine), R-13 (particulate), and R-14 (noble gas) . Channel R-14A remained operable, providing monitoring for iodine and noble gases, as required by Technical Specifications Table 3.5-5 Action 4 ~ Channel R-14A also continuously collected samples for particulate monitoring, as required by Table 3.5-5 Action 5 and Table 4.12-2 Item E. The common sample pump was restarted at approximately 1544 EDST.

E. METHOD OF DISCOVERY:

This event was immediately apparent due to Main Control Board alarms and indications in the Control Room when power from Circuit 751 was lost. These included Main Control Board Annunciator E-14 (LOSS B INSTR. BUS) and the indicating lights for bus 14 and bus 18 supply breakers.

NRC FORH 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISS ION APPROVED BY OHB NO. 3150.0104 (5-92) EXPIRES 5/31/95 ESTIHATEO BURDEN PER RESPONSE TO COHPLY WITH THIS INFORHATION COLLECTION REOUEST: 50.0 HRS.

FORWARD COHHEHTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, TEXT CONTINUATION WASHINGTON, DC 20555 0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHEN'I AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUHBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVI SION YEAR R.E. Ginna Nuclear Power Plant 05000244 NUHBER NUMBER 5OF8 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

F. OPERATOR ACTION:

Following the undervoltage condition on buses 14 and 18, the "A" Emergency D/G automatically started and reenergized these buses.

The Control Room operators performed the appropriate actions to verify that the "A" Emergency D/G was operating properly, safeguards buses 14 and 18 were energized, and Instrument Bus "B" was energized.

When Instrument Bus "B" was reenergized, Rod Control generated an automatic signal to move control rods out. The Control Room operator noted this rod motion and tranferred Rod Control to manual. When the automatic signal stabilized, rods were transferred back to automatic (at approximately 1535 EDST).

Letdown line flow and pressure were oscillating, and the demand signal for the letdown pressure control valve (PCV-135) was cycling in phase with these oscillations. PCV-135 was placed in manual to stabilize the letdown line parameters. Subsequently, PCV-135 was returned to automatic operation after letdown line parameters were stabilized.

The Shift Supervisor notified higher supervision of the loss of Circuit 751, and contacted Energy Operations personnel to determine the problem with Circuit 751.

The Control Room operators restored offsite power (from Circuit 767) to buses 14 and 18, stopped the "A" Emergency D/G, and realigned it for auto standby.

Subsequently, the Shift Supervisor notified the NRC at approximately 1754 EDST per 10 CFR 50.72 (b) (2) (ii).

G. SAFETY SYSTEM RESPONSES'll safeguards equipment functioned properly. The "A" Emergency D/G automatically started due to the undervoltage condition on buses 14 and 18, displayed proper voltage and frequency, and reenergized safeguards buses 14 and 18 to supply emergency power.

Running containment recirculation fans on bus 14 tripped as designed, and were manually restarted as needed to restore normal cooling to the Containment. Running service water pumps on bus 18 tripped as designed, and the pump selected for autostart started when power was restored to bus 18.

NRC FORH 366A (5-92)

HRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY IIITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MHBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, TEXT CONTINUATION WASHING'ION, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY HAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUEHTIAL REVISION YEAR R.E. Ginna Nuclear Power Plant 05000244 NUMBER NUMBER 6OF8 95 -- 006-- 00 TEXT (If more space is required, use additional copies of HRC Form 366A) (17)

III. CAUSE OF EVENT A. IMMEDIATE CAUSE:

The automatic actuation of the "A" Emergency D/G was due to undervoltage on safeguards buses 14 and 18.

B. INTERMEDIATE CAUSE:

The undervoltage on safeguards buses 14 and 18 was due to the loss of power from Circuit 751.

C. ROOT CAUSE:

The underlying cause of the loss of power from Circuit 751 -was tripping of protective relays for Circuit 751 due to an electrical surge from a lightning strike on an offsite utility pole for Circuit 751.

This event is NUREG-1022 Cause Code (C), External Cause. This loss of power and subsequent start of an Emergency D/G does not meet the NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", definition of a "Maintenance Preventable Functional Failure".

IV. ANALYSIS OF EVENT:

This event is reportable 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) ", in that the starting of the "A" Emergency D/G was an automatic actuation of an ESF system.

HRC FORM 366A (5 92)

NRC FORH 366A U.S ~ NUCLEAR REGULATORY COHMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS IHFORHATION COLLECTIOH REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AHD RECORDS HANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMHISSION ~

TEXT CONTINUATION WASHIHGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3180-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL REVI SION YEAR R.E. Ginna Nuclear Power Plant 05000244 NUMBER NUMBER g5 -- 006-- 00 7 OF 8 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

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

o All reactor control and protection systems performed as designed.

o The "A" Emergency D/G operated as designed by automatically starting and supplying emergency power to safeguards buses 14 and 18.

Circuit 767 remained in operation supplying power to the "B" train safeguards buses; subsequently Circuit 767 was lined up to also supply power to the "A" train safeguards buses as permitted by plant technical specifications.

o Radiation monitor channels R-10B, R-13, and R-14 were temporarily lost. Their redundant monitor (R-14A) remained operable during this event, providing radioactive effluent monitoring for plant ventilation.

Based on the above, safety was assured at itallcantimes.

be concluded that the public's health and V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS'ffsite power was restored to safeguards buses 14 and 18 from Circuit 767, and the "A" Emergency D/G was stopped and realigned for auto standby.

The common sample pump for R-10B, R-13 and R-14 was restarted.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

Options for offsite power configuration to the plant will be reevaluated, to optimize reliability during adverse weather conditions.

NRC FORM 366A (5 92)

NRC'ORH 366A U.S ~ NUCLEAR REGULATORY COHHISSIOH APPROVED BY OHB NO. 3150-0104 (5.92) EXP I RES 5/31/95 ESTIHATED BURDEH PER RESPONSE TO COHPLY HITH THIS IHFORHATION COLLECTIOH REQUEST: 50.0 NRS.

FORNARD COHHEHTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, TEXT CONTINUATION UASHINGTON, DC 20555-0001 AND TO THE PAPERIJORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHENT AND BUDGET NASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET HUHBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVI SION YEAR R.E. Ginna Nuclear Power Plant 05000244 HUNGER NUHBER 8 OF 8 95 -- 006-- 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

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: LERs91-002, 92-007, and 94-012 were similar events with similar root causes (start of an Emergency D/G due to loss of offsite power from external causes).

C. SPECIAL COMMENTS:

None NRC FORH 366A (5-92)