ML19105A194

LER 1975-022-00 for Surry 2 Re Setpoint Drift in Nonconservative Direction, Contrary to Tech Spec 2.3.A.2

ML19105A194
Person / Time
Site:	Surry
Issue date:	01/22/1976
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/RGN-II
References
Serial No. 869 LER 1975-022-00
Download: ML19105A194 (6)

Text

• . *-:~:

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"*yi:ROINI.A:

RI~H~<>ND, ::VIR~INI4 I , ,

Mr ... Norman c~,l'fu~~ley, .Directo.r.*

. Off ice of Inspection .and .Enf orcefueri.t .

• united States Nuclear Reguiatory;Comµu:asic,,n:.'::

.Region. It -. Suite 818 . . . . Dqck~t: No.

• 50.-281_

• . 230 Peachtree Street, .Northwest

• Li~ense N.6. DPR-37 *

.At~anta, *Georgi~*.*. *:_;30303' .. '* i . .. *1*.:.**<.:*

'. '..**. '} ' . ._;-..

. . De~r i~ ~ Mot:1eley: ...... *  ;.,.,:.,

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. . Pi.trsuat1t' t9

• Surry Power Stll:tion(iT.ech:ni(;!at Specif,-1.cation 6. 6. B'.,1 ~:

t}:le :v:i.rgin:i.a )Uect;-ic _ap.d .Power Conipan:f he_reby -subni:!-t:s forty. (40) copies

• . of Abnormal Occurrence Repo'i:~. No.* AO-:S2~75:...22.. . ... *. . .

. . . . . *Tp.e _substan~eS of this -report :rui~ been review~d by _the. S~at:_ion* Nttclear *

. Safety. and'* *0perat:ln$*.Co1lllllitte_e and* w;ill be placed. on J:h~ agenda for the next . meeting . .

.. of

• the System.

Nuclear. sa*f .

ety *and ..Operating . ,.

Coinmi.ttee

<:.,Very:

t;ttµ.y yours,.:*,.. '

'it};. *:>>1/vjt~~~

.

• C*. },1 *. Stallings ...

• Vice 'Preelident~Power: Supplf arid *Production Opera.tions Encl~s_ut 7s : , .* .* ...* , , . : . . -', ...

40 .copies.* .of .AO-S2-75-22

~

• .'*cc: . }fr: :Robert:~~ -R~id~<-:* .. . : : ,*.".*

.;_ ~ \ ...

• 692

("-.-,.~ ....

Ll/iiNSEE .EVENT REPORT e Ao-s2-7 s-22 CO~TROL BLOCK:j

• .. 1

,. , , r', *,*- . 6 1 . * [PLEASE PRINT ALL REQUIRED INFORMATION)

LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

@I!) I V I A I SI* Pl SJ 214I Io! o!-lo lo lo lo I o*!-1 o! oj J4 J1 11*'1 lo!* lol 11 7 8 9 15 25 26 . 30 31 32 REPORT

• REPORT CATEGORY TYPE- SOURCE OOCKl;T NUMBER EVENT DATE REPORT DATE

@ill CON'T l p I O I l.!J lJJ I 01 s1 01-10 J2 !8 ll I I 1 I 2 I 11 9 J .1J s1 1°1 1 12 1°1 7 161*

7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION

- joj2j I While operating at 100 per_ cent power Channei 3 for overtemperature ~T indicated 132 I 7 89 ~

!oja! 1* per cent while Channel 1 and 2 indicated 118. _per cent. This was a setpoint drift in l 7 8 9 80 joj4j~j_t_h_e_n_o_n_c_o_n_s_e_~_a_ti_v_e_d_i_*r_e_c_t_i_o_n~,_a_n-d-w_a_s_c_o_n_t-r_a_r~y.;..*_t_o~T-e_c_m_i_*c_a_1_s~p~e_c~i_f_i_c_a_t_i_o_n~2_.3_.A_._2_.*_~I 7 8 9 80 joj5f~!_A~p_o_w_e_r_r_a_m~p_d_o~ __w_a_s_i_*n_i_t_i_a_t_e_d_u_n_t_i_l~t-h_e_c_~_n_n_e_l_3_.__ b_i_s.....

ta_b_l~e-s~.c-o_u_l.;..d~b-e~p-l_a_c_ed~*~i-n_t_h_e_~I 7 89 . 80 (olsl *~I_t_r_i_.p-*-.....*m_o-d_e-*~T-h_e_b_i_*-_w_e_e_k_l;;.::Y:_c_a_.l_i_b_r_a_t_i_on_c_h_e_c_k_w_a_s_t_h_e_n~p-e_r_fo_rm~e'-d-**.;..**........U.:.p_o_n..;.*.:..P.....l_a_c__in_.g::::....:..<c_o_n_'...;t:..:,)_JJ 7 8 9 ,PRIME 80 SYSTEM CAUSE *COMPONENT COMPONENT .

CODE COOE .COMPONENT CODE SUPPLIER MANUFACTUREFl *VIOLATION

@I?J 7-Ir I A 1* lLJ B 9 10 11

!r !N !s!T! Rj*uJ 12

• 17 ll!J 44 I w I 1- ! 2 *Io I

- 47 L!.I 40**

43 CAUSE DESCRIPTION

• joje!  ! The cause of *this occurrence is not. definitely kno~. When the *channel was placed in I 7 89 . . . * ~

!o!9l J test the out of .specification condition cleared*~ The c~li~ 7ation chec~.revealed two I fil~J ! test point voltages slightly out of specUication high; however, this-*was *.not (con'tJ00I 7 B~

7 9:9 80.

FACILITY *METHOD OF

.w*

_STATUS . '% POWER OTHER *STATUS . DISCOVERY *DISCOVERY. DESCRIPTION Iill] l.!.1 I 11 oj .oj12 _*-' _N_/A_ _ ___,.-, I N/A_____.....,..____.,...._-'-_ _ _ _ _8.....,0 4*~-6-.,,...,_ I 7

[el 7

8

• 0 * ,

9 FORM.'OF ACTIVITY RaEASED

-L~J.

s

• PERSONNEL

• EXPOSURES 10 CONTENT OF *RELEASE 10 11 13 AMOUNT *OF ACTIVITY W **,....__.;N;.;.:..;/A_ _ _ _ _ ___.*1 44 44 45 45

-I.~- N/.A ___,..........

LOCATION _______________.,

OF 'RELEASE

-80 NUMBER TYPE DESCRIPTION

-IIEJ 7

• B 9Io I ol ol 11 W 12 NA

'1:3~.-..:.:.,;...:.:..------------------....... -......__,....,.;.,:.-..--......_........;,.._ _ _ __J80 PERS-ONNEL INJURIES

.. NUMBER

• DESCRIPTION .

EEi 101010 7 B 9 .

I . N/A 11 1'~2;-..- - - - - - - - - - - - - - - - - - - . . . . . ; ._ _ _.._~...;..........;...._............,.._.....__ __JBO Oi=FSITE CONSEQUENCES J1 Isl -NIA 7 B 9' 80

. *Loss OR .DAMAGE TO FACILITY TYPE DESCRIP'llDN IT]fil ~ .._N...._/A 7 8 9 . 10 BO PUBLICITY

_!1jz!* - N/ A 7 B 9. BO ADDITIONAL: FACTORS

.EJfil  !',;Due to the coincidence feature of the overtemperature trips,_ the health ,and sa~ety of I 7 8 9*: BO

[!Jfil ,I;the general p*ublic were not affected by this occurrence.

I 7 8 80

~,}": T. L. Baucom NAME~

• PHONE: (804) 357-3184 GPO *au - 667

e J(

EVENT DESCRIPTION (con't) the channel in test, the high indication condition cleared. (AO-S2-75-22)

CAUSE DESCRIPTION (con_' t) related to the high condition observed. A calibration was performed on the channel and it has functioned normally since being placed back in service.

It is postulated that a faulty meter indication, dirty electrical contacts or similar cause resulted in this occurrence. There are no* .. generic implications, in that no cause was found that would indicate a probl_em in other instrumentation.

Thi_s phenomenon has not occurred before.

Reactor safety was not affected, due to the* coincidence design of the over-temperature !J.T trips. Channels land 2 were functioning normally, thereby providing the required two out of three protective function.

e VIRGINIA. ELECTRIC .A.ND POWER COMP.A.NY RIOHMOND,VIRGINI.A. 23261 January 22,. 1976 Mr. Norman C. Moseley, Director Serial No. 869 Office of Inspection and Enforcement PO&M/ALH:clw United States Nuclear Regulatory Commission Region II - Suite 818 Docket No ,.,.,J2.-::.2.8J.;

230 Peachtree Street, Northwest License No. DPR-37 Atlanta, Georgia 30303

Dear Mr. Moseley:

Pursuant to Surry Power Station Technical Specification 6.6.B.l, the Virginia Electric and Power Company hereby submits forty (40) copies of Abnormal Occurrence Report No . .AQ,~S~=2~.

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and .will be placed on the agenda for the next meeting of .the System Nuclear Safety and Operating Committee.

Very truly yours, ii;. 2/Y;. ~4dmfY C. M. Stallings Vice President-Power Supply and Production Operations Enclosures 40 copies of AO-S2-75-22 cc: Mr. Robert W. Reid j

., I

~ENSEE EVENT REPORT *e AO-S2-75-22 COt,_JTROL BLOCK:

. 1 I I I I I . (PLEASE PRINT ALL REQUIRED INFORMATION) 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

@EJ 7 8 9.

I V I A I SI Pl SI 214I 15I n I o1-*1 o Io Io I oI 0*1-1 .o I 25oI 14 26 I 1 I1 *I 1 Io30I Io 31 I 132I REPORT REPORT 7 8 CATEGORY

@EJ CON'T 1p I o 1

• l1:J 57 58 TYPE.

• SOURCE 59

-w 60 I oI s I o1-1 o 12 I 8 61 OOCKl;T NUMBER 11 68

• I I 1 I 21 69 EVENT CATE i 1 9 I 71 s1 I oI 1 I 2 I oI 74 75 REPORT CATE 71 6 80 I.

EVENT DESCRIPTION

. joj2! I While operating at 100 per cent power Channel 3 for overtemperature b.T indicated 132 l 7 8 9 80 tol3! ! per cent wll.ile Channel 1 and 2 indicated 118. per cent. This was a setpoint drift in l 7 89 ~

lol4! ~!_t_h_e_n_*o_n_c_o_n__s_e_rv_a_t_i_v_e_d_i._r_e_c_t_i_o_n..,;,_a_n_d_w_a_s_c_o_n_t_r....;.a_r.:..y........t_o_T_e_ch__n_tc_a_1__s_p::..e_c_i_.f_i_*c....;.a_t_i_*o..;..n_2_._3_*.,.;.A_._2_.*__...,1!

7 8 9 80

!oj5j :I: ;A- -power -----_ rampdown

. ; ; ._ _ _ was_initiated _ _ _ _until ___ the _ Channel _ _ ______.; 3 bistables .could-be placed

____.....__..........._.........,..__..._..:.....,. _ __,...in___ the ___J*I 7 89 *. 80 re ts! -~,_t""."r_J.;.;.;.p":-**....;m;;..o;;..d;;..e;;...;......;T;.;h..;..e__b;..;i;;.-...;w_e_e_k......l;;.:Y:.,....;C;.;a;.;l;;..i~b,.;;r;.;a;.:t_i_o...;.n:......:c...:..h.:..;e,.;;c_k:......:w_a...:..s......:t..:..h:.;.e..:..n_.~p..:,e_r_f..:.o..:.rm.::...e..:..d_.__.:.U:..p..:..on~p~la.:.c.:.1:.:.*n:.::g::........:.<c:..o:..:n.:.'_t:.:):......11

• 7 8 9 .PR!l>.1E 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOE -COMPONENT CODE SUPPLIER MANUFACTURER VIOLATDN

• 7

@0 Ir IA!' Lu 8 9 10 11 12

!r!N!s!T!R!UJ

• 17

.l!.J 43 44 Iw L1 1.2 Io I

.. 47 liJ 48, CAUSE DESCRIPTION *

~,! The cause of *this occurrence is not definitely .known~ When *the channel was placed in!

7 8 9 80 jojsj J* test the *o.ut *of specification condition .cleared*.

• The calibration* ~heck* revealed two I 7 *0 9

-~ I. test point _voltages slightly out of specification :high; 'however, this.was not (con'tr,*

8 80

7 *S .FACILITY .METHOD OF

'STATUS . % *'POWER OTHER STATUS DISCOVERY

• DISCOVERY DESCRIPTION

• lill]

7 8. *

• W 9 . 10 j 1 j Oj OJ -'_N_/A 13

_ _ ____,, W j* 'N/A

• • • FORM. OF . 12 44 45 46 80 ACTIVITY

• CONTENT RELEASED OF* RELEASE -AMOUNT OF ACTIVITY .LOCATION OF RELEASE 7[I~J::

8 I' "uj

• 9

• W 10 *1'.I _1___....;N/ A

____________ *..1

......J44 I *N/A 45 80 PERSONNEL EXPOSURES NUMBER . TYPE DESCRIPTION

• [Iel :I ol ol o! W NA 7 .8 9 11 12 *13 . 80 7 0 s*

• NUMBER

°,

PERS'ONNEL *INJURIES rillJ *rO 1 0 ,

• 11 12 DESCRIPTION .

._,_ _.N __,_A_*._ _ _ _ _ _ _ _ _ ___;,_ _..:..,.._~...;.,,,,._........,..._______,_______ .;.......____J, 00 OFFSITE CONSEQUENCES * .. \ ***:

[ffi] N/A 7 8~9-------------------,~-....;.._-------------------..............-:--~-.........-----------_..;..--------8~0

.LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION 7

EID8 9uJ 10 N/A 80 PUBLICITY

.. (ill}* N/ A

7. 8 9 80

• ADDITIONAL FACTORS

.Elfil I Due to the coincidence feature of the overtemperature trips,. *the health and safety of I 7 89 80.

[ilfil  !. the general public were not affected by this occurrence.

I 7 89 80

• • T. L. Baucom ( )

N A M E , * - - - - - - - - - - - - - - - - - - - PHONE:804 .357-3184 GPO 881*667

EVENT DESCRIPTION (con't) the channel in test, the high indication condition cleared. (AO-S2-75-22)

CAUSE DESCRIPTION (con_' t) related to the high condition observed. A calibration was performed on the channel and it has functioned normally since being placed back in service.

It is postulated that a faulty meter indication, dirty electrical contacts or similar cause resulted in this occurrence. There are no* _generic implications, in that no cause was found that would indicate a problem in other instrumentation.

This phenomenon has not occurred before.

Reactor safety was not affected, due to the-coincidence design of the over-temperature AT *trips. Channels 1 and 2 were functioning normally, thereby providing the required two out of three protective function.