ML20006E984

Forwards Charter for Insp of Events Re Plant Trip of 891226 & Failure of Substation Power Supply Breakers to Sequence Properly Maintaining Power Supply to Reactor Coolant Pumps

ML20006E984
Person / Time
Site:	Prairie Island
Issue date:	12/26/1989
From:	Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Westberg R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20006E979	List: IR 05000282/1989032 ML20006E978 ML20006E984
References
NUDOCS 9002270038
Download: ML20006E984 (2)

Text

{{#Wiki_filter:y , ' c,.,.., ^ I mnish UNITO STATES m 'k NUCLEAR REOULATORY COMMisslON [ s atoion ::: E If. 799 ROOSEVELT ROAD i GLEN ELLYN, ILLINOIS 60137 ....+ DEC 26 BM 1 MEMORANDUH FOR: Rolf Westberg, Reactor Inspector, Plant Systems Section, Engineering Branch, Division of Reactor Safety, RIII FROM: H. J. Miller, Director, Division of Reactor Safety, RIII l

SUBJECT:

AUGMENTED INSPECTION TEAM (AIT) CHARTER s Enclosed for your implementation is the Charter for the inspection of the events associated with the Prairie Island plant trip of December 26 and accompanying t failure of substation power supply breakers to sequence properly maintaining 1 power supply to reactor coolant aumps. This Charter is prepared in accordance i with the NRC Inspection Manual Clapter 0325. The objectives of the AIT are to communicate the facts surrounding this event to Regional and Headquarters management, as well as to identify and communicate any generic safety concerns related to findings and conclusions of the onsite inspection. If you have any questions regarding implementation of the enclosed Charter, please contact either Mr. R. Gardner or Mr. R. Cooper (FTS 388-5578) of my staff or contact me directly. ~ H. J. Miller, Director Division of Reactor Safety

Enclosure:

AIT-Charter cc w/ enclosure: A. B. Davis, RIII C. J. Paperiello,.RIII G. M. Holahan, NRR C. J. Haughney, NRR J. W. Clifford, EDO E..L. Jordan, AE0D C. E. Rossi, NRR S. A. Varga, NRR SRI Prairie Island 1 D. Butler, RIII 900227003s 900212 PDR ADOCK 05000282 G PNU i -a

c. .ly AUGMENTED INSPECTION TEAM (AIT) CHARTER PRAIRIE ISLAND PLANT TRIP AND ACCOMPANYING LOSS OF REACTOR COOLANT PUMP POWER SUPPLIES You and your team are to perform an inspection to accomplish the following: j 1. Develop and validate the sequence of events associated with the plant trip and loss of non-safeguards bus (power supply to the main coolant pumps) that occurred on December 26, 1989 and, to the extent practicable, do the same for the trip occurring on December 21, 1989. Determine what significant differences, if any, exist between these two trips. 2. Determine root cause for the following: a. Opening of both MG set output breakers, b. Failure of the substation breakers to properly sequence to maintain power supply to main coolant pump buses. c. Difficulties in restoring reserve 4160V power to the non-safeguards buses following the event. 3. In evaluating root cause, the following specific items should be addressed: a. Design of (i) rod power supplies and (ii) substation load transfer ,and sequencing functions and equipment. b. Adequacy of the licensee's root cause evaluations of the December 21 event and the associated testing and corrective actions (i.e., failed MG set voltage regulator and cold weather induced sluggish behavior of substation breakers). This would include determining if heating of substation breakers was appropriately maintained. c. Aging of equipment. I 1 l d. Procurement specifications and pre-installation testing of the 1 I substation breakers. u l 4. Review adequacy of the licensee's program for investigating these events. Oversee troubleshooting, testing and analysis of quarantined equipment. 5. Interview plant operators directly involved in the event and determine if operator actions were adequate. l l l l l

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E too moosavait moAo 4: otsw attyn, etta.oss sont .o DECL 3939 n Docket No. 50-282 CAL RI!!-89-02? Docket No. 50-306 j Northern States Power Company ATTN: Mr. C. E. Larson e Vice President, Nuclear Generation 7 414 Mico11et Mall H Minneapolis,MN $5401 j Gentlemen: lw This confirms the telephone conversation between Edward G. Greenaan of this office and you on December 27, 1989, related to the Prairie Island Unit:2 plant trip caused by the opening of both Reactor Protection System motor w generator set output breakers. With regard to this event, we understand that you will: . 1. - Complete an investigation to determine the cause of both Reactor Protection System motor generator set output breakers opening on 12/26/89. 2 Investigate and determine the root cause of the lockout for the 348ky substation Bus 1. 3. In light of the root causes determined for the above, assess your M U 1,l - ] investigation of the trip that occurred on December 21 and determine if n ;'d 4 there -are lessons learned that should be factored into your root c$use gle analysis. 'lI 4. Inform the Augmented Inspection Team leader or the Senior Resident, . "') "e Inspector prior to the performance of any testing of any equipment i.. associated with the Reactor Protection System Motor Generator Sets and .$g their output breakers and the Turbine Generator substation output

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breakers. b a ~ 5. Submit to NRC Region !!! a formal report of your findings and conclusions and corrective actions within 30 days of receipt of this letter. I We also understand that.you will maintain complete documentary evidence of hi your. investigative effort and furnish this evidence to the NRC's Augmented Inspection Team. i .g < fl' We further understand that reactor startup (power operation) will not occur 7; i1: until you have receiv'ed concurrence of the Regional Administrator or his L l' designee. Issuance of this Confimatory Action Letter does not preclude the =i i p issuance of an order requiring implementation of the above comitments. S ' ', JE.$ CONFIRMATORY 1CTIONLETTER 3 L j lm m}th u 1

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h., dDh);. 31. ~ EC2 $89, Northern States Power Co. * . Q.'.# - None of these actions specified herein should be construed to take precedence N~ over actions which you feel necessary to ensure plant and personnel safety. ..' p. S Please advise us innedtately if your understanding differs from that set forth! y above.

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SUMMARY

Test'No. Test Observed Effects Remarks -(a) Loss of field 21 MG-tripped on time "A" phase current E on MG set 21 over current in "A" & in MG set 21 relay. "C" phases, was l'.8 Amps. 22 MG did not trip. Relay operated.as expected.- Bus ~ voltage was 217 volts RMS-for 1.5 seconds before the regulator responded.- (b) Loss of field 21 MG did not trip "A" phase current in on MG set 22 22 MG tripped on time MG set 22 was 1.8' over current in "A"' Amps. Relay operated & "C" phases. as expected. Bus voltage was -218 ' volts RMS for 1.4 seconds before the-regulator responded. -(c) Loss of feedback 21 MG tripped with no MG set 21 tripped on MG set 21 targets after a few on over excitation-seconds delay. and bus over voltage 22 MG tripped on time after a set time' over current;in "A" & delay of 5 seconds. "C" phases. "A" phase current-in MG ' set'22 was 2.1 amps.. Before the current reached the instantaneous trip level, time'over current tripped the breaker. Bus voltage was 345 volts RMS for 3.4 seconds before both breakers tripped. (d) Loss of feedback 21 MG tripped on "A" phase current in on MG set 22. instantaneous over MG set 21 was 2.4 currents in "A" & "C" Amps. Instantaneous

phases, units which are set to to pick up at 2.0 Amps 22 MG tripped with no operated. MG. set 22-targets after'a few tripped on over seconds of delay, excitation and bus over voltage after a set time delay of 5

, NJ q he seconds. ~ Bus voltage was'346 volts RMS for 5 seconds before both breakers tripped. (e) Loss of "A" 21 MG tripped with no This is a less severe phase feedback targets after a few test than TestL(c). on MG set 21. seconds delay. Effects are the same as MG set 22 tripped on time-inTest(c)except:that over currents in "A" & "C" the currents in the-phases. relays were less. Bus voltage was 340 volts RMS for,3,4 seconds before both breakers tripped. (f) Loss of "A"- 21 MG tripped on time This is a less severe. _ phase feedback over currents in "A" & "C" testthanTest(c). on MG set 22, phases. Effects are the same as 22 MG tripped with no in Test (d) except that targets after a few MG set 21 tripped on seconds delay. time over currents as the current level-was below the instantaneous level of 2.0 Amps. Bus voltage-was 345 volts RMS for 3.8 seconds before both breakers tripped. Additional testing was performed which included a loss of prime mover (simulating a loss of MG input power by opening the MG input breaker). 7 (g) Tripped 21 MG set, then 22 MG set. ~# When 21 MG set was tripped, no targets appeared, 21 MG set appeared to motor (it kept speed). Then 22 was tripped; no targets appeared, the units coasted down for about 45 seconds,. then'21 MG output breaker opened. Final state: 22 MG' output breaker closed 21 MG output breaker open no targets. The 21 MG set attempted to maintain voltage and frequency because of'the flywheel affect and became a load on the 22 MG 2

4 ?!j. set. When the 22 MG' set was tripped, the two sets coasted down. together. The 21 MG voltage regulator appeared to respond ' faster than the 22 MG regulator. LAs a result,.the potential feedback circuit (21 MG) responded. faster toLthe decreasing 21 MG output voltage and initiated the opening of the 21 MG output - breaker on overexcitation (decreasing potential feedback increases the exciter voltage). (h) Tripped 22 MG set, then 21 MG set. When 22 MG set was tripped, no targets appeared, 22 MG set appeared to motor (it' kept speed). Then 21 was tripped; no targets appeared, the units coasted down for about 45 seconds, then 21 MG output breaker opened (at 260V output). Final state: 22 MG output breaker closed 21 MG output breaker open no targets.

(i) Tripped 22 MG-set and 21 MG set at the same time.

When both MG sets were tripped; no targets appeared,- then 21 MG output breaker opened (at 260V output). Final state: 22 MG output breaker closed 21 MG output breaker open no targets. The analysis for Test (g) also applies to Tests (h) and (1).; l' 1 3

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c, ,e NO.7 : PAGE 2 OF 2 eg Y / WI e m C KEY (AIR PRESSURE) E 500 PSI (SUPPLY LINE) E 2000 PSI g E S F, GAS M s 1 LEGEND: Q PRESSURE SWITCH (A) 63AH j ,8 W{+ SOLENOID VALVE (B) 63AL',63RG.63CT 8 s (CT REGUL ATOR D 3WAY MANUAL VALVE (D) MANUAL TRIP N %(+ C Q ELECTRO-MECHANICAL VALVE s Co (E) CONTROL VALVE % VALVE MECHANICALLY INTERLOCKED w OUS (VALVE MUST BE OPEN WHEN DOOR IS CLOSED) CHECK VALVE h SAFETY VALVE '.4 'Yo1( & [pg.; -M-MANUAL VALVE O FILTER Trdg",.t$ ;s. @ PRESSURE G AGE ' kN-hl @ HUMIDITY INDICATOR s 1' H8GH PRESSURE AIR FROM SUPPLY SYSTEM

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