Event Notification Report for February 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/18/1999 - 02/19/1999
** EVENT NUMBERS **
35382 35383
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|Power Reactor |Event Number: 35382 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 02/18/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 12:00[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/18/1999|
+------------------------------------------------+EVENT TIME: 10:00[CST]|
| NRC NOTIFIED BY: FERGUSON |LAST UPDATE DATE: 02/18/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE YANDELL R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| Improper sequencing could have allowed a control room fire to create a hot |
| short across any of several main control board hand switches. |
| |
| During corrective actions associated with LER 98-004-00 (submitted to NRC by |
| letter dated November 6, 1998), Wolf Creek Generating Station personnel |
| determined that off-normal procedure OFN RP-017 sequence of actions |
| historically allowed control power to be removed from the "B" train ESF bus |
| before rotating the Normal / Isolate switch to the "Isolate" position. This |
| improper sequencing could have allowed a control room fire to create a hot |
| short across any of several main control board hand switches (i.e., ESW "B", |
| CCW "B", Charging "B", Load Centers on "B" train, Pressurizer Backup |
| Heaters, and Emergency Diesel Generator (EDG) "B"); the most significant of |
| which is the EDG "B." This hot short could potentially result in a loss of |
| availability of any or all of the previously listed components. Because a |
| loss of offsite power and the loss of EDG "A" are assumed coincident with a |
| control room fire, the loss of EDG "B" could result in a station blackout. |
| The resultant scenario is inconsistent with Wolf Creek fire safe shutdown |
| commitments associated with Appendix R of 10CFR50, which are contained in |
| Letter #SLNRC 84-109. |
| |
| As noted above, this is a historical occurrence. Revision 12 of the |
| controlling procedure (OFN RP-017) corrected the improper sequencing. |
| |
| In accordance with NUREG-1022, this event is reportable as a condition |
| outside the design basis of the plant. |
| This issue also constituted a loss of safe shutdown capability and a |
| violation of License Condition 2.C (5), which indicates that Wolf Creek may |
| not make changes to the approved fire protection program which significantly |
| decreases the level of fire protection to the plant without prior NRC |
| approval. Section 2.F of the Operating License requires Wolf Creek to |
| report any violations of Section 2.C of the Operating License to the NRC |
| within 24 hours, |
| |
| The root cause and associated corrective actions will be reported to the NRC |
| in a supplement to LER 98-004 and will include systems affected, actuations |
| and their initiating signals, causes, effect of the event on the plant, |
| actions taken or planned, etc. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
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|Power Reactor |Event Number: 35383 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 02/18/1999|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 21:39[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/18/1999|
+------------------------------------------------+EVENT TIME: 20:40[EST]|
| NRC NOTIFIED BY: BRIAN STETSON |LAST UPDATE DATE: 02/18/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
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EVENT TEXT
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| LEAKAGE OUTSIDE CONTAINMENT EXCEEDED ITS 60 GPH LIMIT. |
| |
| AT 2040 ON 02/18/99, RELIEF VALVE #1E12-F0036 ON THE LINE FROM THE RHR HEAT |
| EXCHANGERS TO THE RCIC SYSTEM WAS DETERMINED TO BE LEAKING AT 75 GPH INTO |
| THE AUXILIARY BUILDING EQUIPMENT DRAIN SUMP. THE RCIC SYSTEM IS ALIGNED TO |
| THE CONDENSATE STORAGE TANK, NOT TO THE SUPPRESSION POOL. IN THE EVENT THAT |
| THE RCIC SYSTEM IS NEEDED IN AN ACCIDENT, IT COULD ALIGN TO THE SUPPRESSION |
| POOL, RESULTING IN SUPPRESSION POOL WATER LEAKING OUT OF CONTAINMENT. THE |
| PLANT IS NOT IN ANY LCO ACTION STATEMENT AT THIS TIME, BUT WHEN REPAIRS TO |
| THE VALVE COMMENCES, THE RCIC SYSTEM WILL BE DECLARED INOPERABLE AND THE |
| LICENSEE WILL ENTER A 14 DAY LCO. THE HPCS SYSTEM HAS BEEN VERIFIED TO BE |
| OPERABLE. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. |
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