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.., a am, n. i On 3/16/84 and again on 3/27/84, whilo shut down for rofueling, a full scram signal was gonorated. No fuol was in tho vossol, and all control rods woro valvod out at 1
tho tino of the ovents. Operations initiated an investigation which concludod that tho scrams occurrod when the pcwor supply for "A" RPS was temporarily intorruptod.
Causo of tho unplanned scram was duo to oporator orror combined with an of f-normal configuration of tho PPS. During both scrams, the oporator f ailed to realize that a f ull scram will occur when tho scra'n ditchargo high lovat signal is bypassod and a loss of power to olthor RPS oc;urs.
Thoro woro no system or componont f alluros during this ovent.
To procludo rocurrenco, Oporations personnot woro councolled o s the cauco of the ovont.
In addltlon, a copy of this report will be forwarded to all licensed operators and tho Tralnlig Dopartment.
0405010486 R40412 PDR ADOCK 05000293 G
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aeRC,are 3e64 W 8 NUCLEl.3 $ SOULATORY COMulgatoes LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
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On 3/16/84 and again on 3/27/84, whilo shut down for refueling, a full scram signal l
was generatod. No fuel was in the vossol, and all control rods woro valved out at the timo of the event. The event occurred when transferring the power supply for tho i
"A" Reactor Protection System (RPS). During the transf er, power to "A" RPS was momentarily interrupted as planned.
In both casos, the operator expected a half scram f rom loss of power to "A" RPS, but recolved a full scram, i
in both casos, the operator initiated an investigation into tho cause of tho scram.
l The Investigation was completed on 3/28/84 and rovealed that when the scram dischargo I
volumo high lovel circuitry is bypassed, Rolays 5AKl8A and SAKl8C are common to both f
RPS channels. Thus, loss of power to olther RPS channel will causo a full RPS scram.
The scram dischargo volume high lovel scram had boon bypassed vio key lock switch l
approximately two wooks prior to tho first event in support of a modification to tho l
CRO scram dischargo volume system.
Root cause of the ovents is attributed to cognitive operator error.
Specifically, the operators f ailed to realize that a f ull scram would occur whon in tho above-montioned configuration and power to olther channel of tho RPS was intorruptod. Wo bollovo proceduros are adequato in that if the operators had realized that a full scram would occur, they would havo expected the scram and planned accordingly.
To reduco the probability of a similar ovent, Operations personnel woro immodlotoly counsolled on the cause of the scrams upon complotton of the investigation.
In addition, a copy of this roport will be sent to all llconsed operators and the Training Dopartment.
This ovont did not impact iho health and sofoty of the publIc.
A search of f ailuro records Indicatos no provfous occurrences of a similar naturo.
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WOETON ED150N COMPANY 500 WOVLaTON STREET 50eTON. MA55AONUSETTs 02199 wgLLIAM D. HARRINGTON April i2, 1984 e:................
BECo Ltr. #84-053 Dr. Thomas E. Murley Regional Administrator, Region i U.S. Nuclear Regulatory Commission 631 Park Avenuo King of Prussia, PA 19406 Docket Number 50-293 License DPR-35
Dear Sir:
The attached Licensoo Event Roport 84-001-00, " Scram Signal During Power Transfer," is hereby submitted in accordanco with the requiremonts of 4
10CFR50.73.
If there are any questions on this subject, please do not hesitato to contact me.
Respectfully submitted, i
es!-
i W. D. Harrington PHicaw Enclosuro:
LER 84-001-00 cc Document Control Dosk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Standard DECO LER Distribution op '
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| 05000293/LER-1984-001, :on 840316 & 27,full Scram Signal Generated.No Fuel in Vessel & All Control Rods Valved Out During Events. Caused by Personnel Error.Operations Personnel Counseled on Cause of Event |
- on 840316 & 27,full Scram Signal Generated.No Fuel in Vessel & All Control Rods Valved Out During Events. Caused by Personnel Error.Operations Personnel Counseled on Cause of Event
| | | 05000293/LER-1984-002, :on 840318,during Refueling Outage,Hfa Relay in Reactor Protection Sys Found to Be Hot & Smoking.Cause Attributed to Generic Hfa Relay Problems.Corrective Actions Will Be Included in IE Bulletin 84-02 Response |
- on 840318,during Refueling Outage,Hfa Relay in Reactor Protection Sys Found to Be Hot & Smoking.Cause Attributed to Generic Hfa Relay Problems.Corrective Actions Will Be Included in IE Bulletin 84-02 Response
| | | 05000293/LER-1984-003, :on 840319,discovered Once/Cycle Diesel Generator Fire Pump Surveillance Test Not Performed Per Tech Specs.Pump Declared Inoperable.Caused by Incorrect Info in Surveillance Tracking Program Data Base |
- on 840319,discovered Once/Cycle Diesel Generator Fire Pump Surveillance Test Not Performed Per Tech Specs.Pump Declared Inoperable.Caused by Incorrect Info in Surveillance Tracking Program Data Base
| | | 05000293/LER-1984-008, :on 840521,HFA Relay in Reactor Protection Sys Found Hot & Smoking.Caused by Generic Hfa Relay Problem. Relay de-energized & Replaced W/Ge Century Series Relay |
- on 840521,HFA Relay in Reactor Protection Sys Found Hot & Smoking.Caused by Generic Hfa Relay Problem. Relay de-energized & Replaced W/Ge Century Series Relay
| | | 05000293/LER-1984-009, :on 840626,HFA Relay in Primary Containment Isolation Sys Found Hot & Smoking.Cause Related to Previously Identified Generic Hfa Relay Problems.Relay Deenergized & Replaced |
- on 840626,HFA Relay in Primary Containment Isolation Sys Found Hot & Smoking.Cause Related to Previously Identified Generic Hfa Relay Problems.Relay Deenergized & Replaced
| | | 05000293/LER-1984-010, :on 840822,determined That CRD Collet Retainer Tube Had Longitudinal through-wall Crack.Caused by IGSCC in Cold Worked & Weld Sensitized Stainless Steel.Matl Replaced & Metallurgically Examined |
- on 840822,determined That CRD Collet Retainer Tube Had Longitudinal through-wall Crack.Caused by IGSCC in Cold Worked & Weld Sensitized Stainless Steel.Matl Replaced & Metallurgically Examined
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000293/LER-1984-011, :on 840828,emergency Diesel Generator a Inadvertently Started.Caused by Spurious ESF Signal.Diesel Generator Secured |
- on 840828,emergency Diesel Generator a Inadvertently Started.Caused by Spurious ESF Signal.Diesel Generator Secured
| | | 05000293/LER-1984-012, :on 840920,emergency Diesel Generator B Inadvertently Started During Surveillance Test.Caused by Unplanned Start Due to Nonlicensed Personnel Error.Diesel Secured & Personnel Counseled |
- on 840920,emergency Diesel Generator B Inadvertently Started During Surveillance Test.Caused by Unplanned Start Due to Nonlicensed Personnel Error.Diesel Secured & Personnel Counseled
| | | 05000293/LER-1984-013, :on 840920,indications of Cracking in Area of Weld Connecting Reactor Vessel Jet Pump Instrumentation Nozzle to Jet Pump Instrumentation Identified.Caused by Band of 304SS Matl in Weld Assembly.Weld Grinded |
- on 840920,indications of Cracking in Area of Weld Connecting Reactor Vessel Jet Pump Instrumentation Nozzle to Jet Pump Instrumentation Identified.Caused by Band of 304SS Matl in Weld Assembly.Weld Grinded
| | | 05000293/LER-1984-014, :on 840928,while Shut Down for Refueling, Reactor Scram Signal Generated Through Reactor Protection Sys.Caused by Procedural Inadequacy.New Procedure Drafted to Provide Guidance for cross-tying Buses |
- on 840928,while Shut Down for Refueling, Reactor Scram Signal Generated Through Reactor Protection Sys.Caused by Procedural Inadequacy.New Procedure Drafted to Provide Guidance for cross-tying Buses
| | | 05000293/LER-1984-015, :on 840929,during Refuel Outage,Unplanned Actuation of Containment Spray Sys Occurred.Caused When Electrician Stroked Upper Drywell Outboard Isolation Valve. Personnel Counseled |
- on 840929,during Refuel Outage,Unplanned Actuation of Containment Spray Sys Occurred.Caused When Electrician Stroked Upper Drywell Outboard Isolation Valve. Personnel Counseled
| | | 05000293/LER-1984-016, :on 841207,power Lost to 120-volt Ac Safeguards Bus (Y4) B.Caused by non-licensed Cognitive Personnel Error. Power Loss Resulted in Group 6 Containment Isolation. Personnel Counseled |
- on 841207,power Lost to 120-volt Ac Safeguards Bus (Y4) B.Caused by non-licensed Cognitive Personnel Error. Power Loss Resulted in Group 6 Containment Isolation. Personnel Counseled
| | | 05000293/LER-1984-017, :841219,temporary Loss of Offsite Power Experienced.Caused by Operator Activating Two Stuck Breaker Protection Switches W/O Resetting Corresponding Lockout Relays.Personnel Counseled |
- 841219,temporary Loss of Offsite Power Experienced.Caused by Operator Activating Two Stuck Breaker Protection Switches W/O Resetting Corresponding Lockout Relays.Personnel Counseled
| | | 05000293/LER-1984-018, :on 841220,while Shutdown for Refueling,Lpci Valve Found Inoperable.Caused by Worn Teeth on Splined Insert Gear of Motor Operator.Motor Operator Refurbished |
- on 841220,while Shutdown for Refueling,Lpci Valve Found Inoperable.Caused by Worn Teeth on Splined Insert Gear of Motor Operator.Motor Operator Refurbished
| | | 05000293/LER-1984-019, :on 841225,Group 1 Containment Isolation Signal Received.Caused by Excess Cooling in Area of Ref Leg a, Inhibiting Ability of Condensing Chamber to Provide Adequate Makeup.Proposed Mods Being Evaluated |
- on 841225,Group 1 Containment Isolation Signal Received.Caused by Excess Cooling in Area of Ref Leg a, Inhibiting Ability of Condensing Chamber to Provide Adequate Makeup.Proposed Mods Being Evaluated
| | | 05000293/LER-1984-020, :on 841225,Group 1 Containment Isolation Received Due to High Reactor Water Level Signal.Caused by LPCI Valve Not Fully Seated.Lpci Valve Isolated & Reactor Water Level lowered.w/850124 Ltr |
- on 841225,Group 1 Containment Isolation Received Due to High Reactor Water Level Signal.Caused by LPCI Valve Not Fully Seated.Lpci Valve Isolated & Reactor Water Level lowered.w/850124 Ltr
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