ML18348A202

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LER 1977-054-00 Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus
ML18348A202
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/21/1977
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1977-054-00, LER 1977-057-00, LER 1977-058-00
Download: ML18348A202 (5)
v • d • e


Text

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consumers

  • Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
  • Area Code 517 788-0550 December 21, 1977 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR PftLISADES PLANT - ER-77-054, ER-77-057 and ER-77-058 Attached are three reportable occurrences for the Palisades Plant. Event Repo::ct 77-058 was a prompt reporta.ble event that was identified by TWX dated December 12, 1977.

David P Hoffman Assistant Nuclear Licensing Administrator CC: _l\.Schwencer, USNRC DEC 2 7 1977

1..'

.ENSEE EVENT REPORT *- _ Palisades CONTROL BLOCK: I* . I*. I *. I

  • I*. I; I (~LEASE PRINT ALL REQUIRED INFORMATION]
1. 6 LICENSE EVEtlT LICENSE NUMBER TYPE TYPE I o I o1--1 o I oI o I o Io 1-*I o I o I 14111111111 I oI 3 I 15 25 26 30 31 32 DOCKET NUMBER EVENT CATE REPORT CATE

@ElcON'T 7 8*

r *I *I58 57 1015101~101215151 61 68 1111121111111 69 74 1112121011111 75 80

. EVENT DESCRIPTION

. 1* lal 21 I While raising reactor power, .four coincident in-core alarms were received at 95. 6%

~

7 8 9 80.

Iola!_ I power. Event reoccurred on 11-22-77 and 11-23-77. On each occurence, power was I 7 8 9 80 lol4l I

  • i l reduced.to clear the alarms and a power distribution map was qbtained per Technical I 7 B 9 80 lol51 I Specii'ication 3.11.B. During the occurence on 11-23-77, one incore alarm remained I 7 8 9 80 lolsl I after a power* reduction to 85%; power was maintained less than 85% until the Xenon I 7 8 9 PRIME 80

, SYSTEM CAUSE COMPONENT COMPONENT (cont'd)

CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

@El IIIDI L£.l I z I z I zI zl z I z I l]J I z I 9 I9 19 I l1LJ 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Iola! I In-core alarms were caused by a Xehon oscilJatjon.* On J 1-23-17, a procednre +a dampen I 7 8 9 60 lojgj I the Xenon oscillation was successfully implemented. I

,.97 EE]

8 9 F.o!IClllTY STATUS  % POWER OTHER STATUS lo 1916 I*...._!_ _N_A_ ___.I METHOD OF DISCOVERY

~

DISCOVERY DESCRIPTION NA 80 80 7 8 12:..J 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT \

7 rn 8 RELEASED L!.J 9

OF RELEASE l!J 10 I

AMOUNT OF ACTIVITY NA

,~1-----------------------'44

-I 45 NA l,OCATION OF RELEASE 80 PER_SONNEL EXPOSURES

[El L9IOIOI l!J NUMBER

  • TYPE DESCRIPTION L-------NA________________________________________~

7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION EEJ lalalal'11 7 8 9 12 80 PROBABLE CONSEQUENCES tillJa s 7

NA 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

~~ NA 7 8 9 10 80 PUBLICITY

[IE] NA 7 8 9 80 ADDITIONAL FACTORS A'1R1 I (Event Description-cont'd) oscillation was dampened. Power distribution maps J

~9 80

~ I justified operation with the in-core alarm. No LH GR limits were exceeded. (ER 77-054) I 7 8 9 80

    • .----------------**-*~-

____ :_, ____. .;.___ '*-----=-*--~---~*.:. *' -- - ....~-

. .ENSEE EVENT. REPORT Palisades COl\JTROL BLOCK: I . I

  • I* . ,. I . I L [PLEASE PRINT ALL REQUIRED INFORMATION) 1 . 6.

" IJCENSEE LICENSE EVENT

,*NAME LICENSE NUMBER TYPE TYPE IM,. II Pl Al 111 I 10101-10101010101-10.10 I 1411 1 1 11111 1° 1332I 7 B 9 14 15 25. 26 30 31

- REPORT REPORT TYPE. COCK~ REPORT. CATE.

.J I610 I 5 I 0 1-1 ° I 2 I 5 I *568I SOURCE NUMBER EVENT. CATE

@El CON'T l

  • I
  • I ~ 12.' 11 I 21 o15 I 7 I 71 1112121111111 7 8 57 58 59 60 69 74 75 80 EVENT DESCRIPTION lol2I I During monthly surveillan.ce of the Reactor Protection System TM/LP setpoints, the I 7 8 9 80 lol3l LI .....i;P.=.r.::::.e::,ss::_ur~e:::.....::s;:..::e:...::t::....tP:.:;:O:,;;i,::n~t_,;;_fo::.;,;'r;;.,...:c~h~ann~~e:.:l;......:::C:.....::.w.=::a.:;.s.-f::.:o~un~d=--.i;t:.::;o:.......l;!b£e...=.l.1..7:::.47J.......Jp~s:..;i:.::.a=-....!i..;.n=.:=s:.i.t~e.5!a"=!d--:..:.o=..f-l._7.1...5..,.0~p""s1..1i..,.a!t.-..>la.,.s_ _~I 7 .8 9 80 lal4 f LI_r_e_qui_*r_e_d_,_b....,Y_._T_._s_._2_._3_.4_._._R_e_m_a.i_*_n_i_n_g_t_h_r_e_e_c_h_an_n_e_l_s_h_a_d_p_..r_o_p_e_r_s_e_t_p_o_in_t.._s__.._:EJ_v_.e_n_u....~_11_o_n_--~I 7 B 9 BO

~ I repetitive. Setpoint was returned tc:i an acceptable value. I 7 8 9 (ER-77-57) BO lolsl 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION.

7

@El I 8 9 10 II A I l!J . I I IN Is IT I R I u I 11 12 17 10_1 43

-I GI 0 I 810 I 44 47 w 48 CAUSE DESCRIPTION lolsl I Non-conse~vative.setpoint caused by instrument dri-ft (GE ~fA.C Mod 562) Amount of drift I 7 8 9 80 lajsj I (3 psi) is within instrument accuracy of+/- 0.5%. A setpoint chang*e to raise the I 7 8 9 80

, . , , I instrwnent setJ;Jojnt

. ! BS js being ;processed BO I

l ~~~~ ~~~g~ER';!'

w

% POWER OTHER STATUS DISCOVERY DESCRIPTION EE] .* LIJ I0 I 9 I 8 I NA I NA 7 B 9 10 12 13 44 45 46 BO FORM OF

......J' ACTIVITY CONTENT 7

rn 8 RELEASED 9

W OF RE:LEASE.

l_zJ 10

  • '-j_ _

11 AMOUNT OF ACTIVITY

_,;;;:N~A 44 45 NA LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7

[ill] lol olol B 9 11 w 12 13 NA BO PERSONNEL INJURIES NUMBER DESCRIPTION

~ lol o!ol L-....-----~N=A;______________________________________________~

7 8 9 11 12 BO PROBABLE CONSEQUENCES BE 7 8 9 NA BO LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

[I§ l2J N 7 8 9 10 80 PUBLICITY NA EI?J 7 B 9 80

. , AODmDNAL FACTORS NA 8 9 80 NA

~

7 8 9 80

. . . .ENSEE **EVENT REPORT .

  • e Palisades

~ONTROL BLOCK:j I* I I I L [PLEASE PRINT ALL REQUIRED INFORMATION]

1 6

  • l:ICENSEE LICENSE EVENT

~ r NAME LICENSE NUMBER TYPE TYPE

~IMl'IIPIAI Lill I 0 1°1-1°1°1°1°1°1-1°1°1 I 41 1 I 1 I 1 I 1 1 I 0 11 I 7 8 9 14 15 25 26 30 31 32 DOCKl;T NUMBER EVENT DATE REPORT DATE 7

@mcoN'T 8

r

  • I *I 57 58 I61ol5 lo I-lo 121512

. 68 I l1l2l1l1l1l1l 69 74 1112121111111 75 80 EVENT DESCRIPTION lol2I f During. normal stead.y-state operation, the 'R' bus. became de-energized, caus1ng a I 7 8 9 ea 10131.1 complete loss of offsite power and resulting in a loss of main condenser cooling I 7 8 9 80 7

@EJ8 9I water The reactor was marnrn.J ly tripped. The primary plant* was stab; J j zed j n tb_e hot 80

.I lolsl I condition and was borated. Technical Specifications 3.1.1.a and 3.7.1 were viqlated I 7 8 9 80 lolsl I Both diesel generators operated normally to supply electrical power during the 1.5 I 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMF'ONENT (cont I d)

COOE CODE COMPONENT CODE SUPPLIER MANUFACTURER *VIOLATION

@0 I E!A I ~ I z I z I z I ZI z I z I ~ IZ 19 19191 l:_j (ER~77-58) 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Iola! I The cause of the 'R' bus loss is unknown at this t~me. To mitigate the consequences I 7 8 9 80 lojsj I of future 'R' bus losses, the tripping scheme for the 'R' bus has been modified so I 7 8

.. 1. 0 j that a signal froII). the stripping relay (486 s-x) will trip neither the 345 KV supply 89!;--------,---.-----------~-_,..-----------~---,(--t-,-d~)--8-10 8

l FACILITY METHOD OF con STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 7

EEi8 L!J.

9 11

. 10 I 0 I 012I 13 NA 44 L~

45 NA 4~6---------------------'

FOAM OF 80 ACTIVITY CONTENT 7

rn 8 RELEASED

~

9 OF(ftl,ASEl..,.__1_5_A~-o-c~_"t:i._\_9_~_t_c_T_IV_ITY_ ___,I 10 11 44 45 LOCATION OF RELEASE Secondary water to atmosphere 80

  • PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION EE}. I 0 I 0 I 0 I ~ NA 7 8 9 11 12 13 80 PERS.ONNEL INJURIES **---

NUMBER DESCRIPTION EEi lol olol11 7 8 9 12 NA 80 PROBABLE CONSEQUENCES

-~ NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION r2E. ~

7 8 9 10 NA 80 PUBLICITY G£I8 9 7

NA 80 ADDITIONAL FACTORS I (Amount of Activity- cont'd) microcuries of I-131; 7.5 microcuries of I-133.

BO 7

GE8 9 80

Even~ pescription, (cont'd):

e h~~rs that off-site power was not available. This event similar to ER 77-055.

(ER 77-058)

Cause Description (cont'd):

breaker 27-R8 nor t.he low side breakers feeding the 2400 and 4l60 volt buses.

The 27-R8 break.er will trip from the transformer bank differential relays, and thermal trips for the feeder breakers have been retained. This scheme retains electrical fault protection, yet will prevent plant trips from spurious action of the 'R' bus stripping relay.

To determine the source of the 'R' bus stripping signals, the 486 S-X relay has been instrumented so that recorder traces can be obtained in the event future trips occur .

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