ML20236N791

Rev 0 to Procedure 2.2.126, Atws

ML20236N791
Person / Time
Site:	Pilgrim
Issue date:	04/28/1982
From:	BOSTON EDISON CO.
To:
Shared Package
ML20236N770	List: ML20236N767 ML20236N775 ML20236N779 ML20236N781 ML20236N784 ML20236N787 ML20236N791 ML20236N817 ML20236N847
References
FOIA-87-644 2.2.126, NUDOCS 8711170010
Download: ML20236N791 (4)

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30S"ON 07 I';

ISOn COVRANY ;

i NUCLEAR OPERATIONS DEPARTMINT

?ILCRIM NUCLIAR PO'ER STATION Procedure No.

2.2.126

)

A. T. k'. S.

a l

i List of Effective Pages 2.2.126-1 Rev. 0 2.2.126-2 Rev. 0 2.2.126-3, Rev. 0 2.2.126-4 Nev. 0 4

Attachments None i

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Approved ne RC' Chair-

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i 2.-2,126-1 Rev. 0 l

8711170010 871112 FDR FOIA

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\\ PURPOSE i.

J To provide a detailed. instruction for' operating personnel to ' operate (the i

i ATWS System.

L _ et,.

j II. - DISCUSSION A

i A.

General 1

One of.the most severe transients postulated for a nuclear, system is "A.T.W.S.", Anticipated Transient Without-Scram. l The worst - case 'of

'l A.T.W.S. would be an MSIV closure without a scram at.100% power, l

' with no loss of f of f-site power.

,,H-L 4.

i' 1

During the 1980 and 1981 refueling' outages the "ATWS-RPT/AR1 equip-l L

ment was installed that monitors reactor vesseli ressure and' vater'i p

level in a redundant and/ diverse manner from the Reactor Protection j

1 System. The trip outputs from'this essentRilly independent; system will perform t,he following functions.upon detection either H1'Hi-reactor pressure.or Low-Low water level.

1.

Trip both.Re ctor Recirculation Pumps (RPT) (the field breakers of the pump motors will receive'the trip signal from ATWS logic)

J 2.

(ARI) Automatic Rod' Insertion Energize two '(2) independent backup scram solonoid vdives.. thus,

discharging the scram pilot valve air header. (SPVAH). This action duplicates a function' performed by.the Reactor Protection System (control-rod insertion).

L.

Automatic Response of System l'

.t 1.

To initiate the ATWS trip sequence, the f ollowing signals amust ~ be -

received,b the ATVS logic:

f a.

two high-high pressure signals i

1 4-b.

or, two low-low Rx. water leve'l signals or one high-high pressure and one low-low.Rx. water icvel a

c.

i d.

or, a and b simultaneously The current trip settings in the?ATWSslogi,c are:

a.

high-high pressure, 1175-ps1g b.

low-low water. level (-)47 inches of water (corresponding' to (-)50 inches to (+) 50 inches. measured range) 2.

ATWS-RPT Time Delay'

+

r 1

The ATWS-RPT logic is delayed for ten- (10) seconds before tripping of the recirculation pumps, af ter the initiating process signals 4 e

~

'(pressure and/or level are received).

Only keveF Hi-Hi pressure M

l, initiates RPT immediately.

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Rev.

a

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1

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9 l

3.

ATWS-AR1 Manual (Ope [ator) Actuation p'

t 3

,I At the main control room panel (C905) two push buttons are provided~for each ATWS-ARI division;. When both push buttons dre'

)

used and depresued for one. division the ATWS-ARI sequence is l

i initiated manually (by operator action) f o'r that division, thus i

venting.the. SPVAH and inserting the control rods.

l l

III.

REFERENCE l

i a

^

i i

IV.

PREREQUISITES

.i A.

Power Supplies Energized.

1.

120 Vac from safeguard but Y3 Div. 1 2.

120 Vac from Safeguard but Y4 Div. 2 3.

125 VDC from D-36 Div. 1 4.

125 VDC from D-37 Div. 2 V.

LIMITATIONS

.A. Limiting Conditions of Operations - Technical Specification t.

I.

L

'l a

3

(

B.

Administrative Limits l

t VII.

OPERATING PROCEDURE Normal During normal operation the ATWS system requires no operator action.

1 Operator Actuation a

At the main control room panel (C905) two push buttons are provided for each ATWS-ARI division. When both push buttons ar'e used and depressed,

?

2 2.126-3 Rev. 0 l

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w i.3 -

.y the ATWS-ARI sequence is initiated manually.for daytidivision, thus:

venting the SPVAH and inserting the control, rods'.

4

')

li Because this type of control rod insertion is slower than. norma'l (RPS)

. scram operation (approximatley 35 to 40 secoads f or completion) the-J ATWS-AR1 trip logic will remain activitated f or 60 seconds once the.,

jb

'$ 3 mandal.getuation is, initiated.. Due to the newly installedjair-dump,.

oystem,.although the ATWS-ARI logic' has already r.eset, manual resetaof-the, SPVAH is needed to close the scram-valves. fThis is. accomplished

' ' +

'by placing the scram-discharge vents and drain hand switch on panel-905 l

I to the isolate position..Once the SPVAH Lo' air pressure-a arm has?

l cleared the hand switch can be returned to normal, thus. providing;a, drain,.

path for.the scram discharge 1volums, tank.

g e n The ATWS racks 2277. and 2278 located 'in the' Rx. bid,. 51el. nex[ to t

the RPS- (Yarway Racks) 2202 and 2206 have the transmitters and. electronics 3

I monitoring,Rx. pressure and level', ' Individual alarm units are also independen'ly after an ATVS!

mounted on:these racks and can be reset t

trip. Power.available lights are also mounted at the top of these' racks q

and should be checked daily. The ATWS trouble alarm on Panel 905 in the main control room monitors this power. available along with gross,

-j q

failure of the transmitters and will alarm if there is any trouble.-

Operator action on receiving' this alarm would be to, check the DC/AC

]

inverters in the upper and lower switch geatrrooms:for power, and check-individual pressure and level readings locally at racks 2277 and 2278 for transmitter failure.

1 s

i The small neon lamps mounted locally at. racks 2277.and 2278 in a.

vertical row monitor continuity for.cach trip circuit.

If'only h of

~~

~C an ATWS" trip channel is activated the small neon, lamp would. be glowjpg.

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brightly. A full ATWS trip would not show any bright lights..

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April 8.: 1983

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, 3 aEco 1.tr. #83-86 1

i RECORD TYPE:_ A00 I, l

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EEWORDS Dbl 6' Regional Administrator. Region 1 U. S. Mucleer Regulatory Comadesion

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631 Park Avenue King of Prussia FA 19406 gr.

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h,NTROLLED OtSTRIBull0N7 Docket Number 50-293 License DPR-35 YES O NO E Dear Sirt i

COMPONENT f:

The attached Licensee Event Report 83-012/03L-0. "ATVS Neon Indicator

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Lights" is hereby submitted in accordance with the requirements of Pilgris

]

Nuclear Power Stetton Technical Specification 6.9.3.2.b.

Q.uST i 1

!3101667.

j If there are any questions on this subject, please contact us.

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t Respectfully submitted.

If (BNM c )' !

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V. D. ftarrington d

Senior Vice President Nuclear r

i CC1J dup Lit 015TalsuT0!R (stCo.)

i Enclonure LER 83-012/03L-o t

MessN W. C. brington Ms; K. Caleco m b

cc: Doc nent Co trol Desk

. J. E. Houard N00 Licensing (Jack felten)

U. S. Nuclear Regulatory Commissio" J. M. Ballectine pnp 5 Records Center Superviser Washingt.,n. D.C.

205!,5 '

W. J. Arustrong mutt'e4sident4nspector : 'N M. F. Brennen C.J.M. LettertiocA for LERs

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ey g g g g,,, y g Standard BECo 1.ER Distribution P. T. $lerdiello 3

S. M. MclMh M. 7. #4cteugh11e m.,, c.,

A. W. Morist J. W. RicholSen RELEASED A. L. Ousen P. E. Mestrangelo L !.M ',

APR 12 G83

9. E. Ser. feed i

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,0,U_$lyDl5TaltuT10M OWj Document Conteel Desk Mr. J. t. Mtmeelvrtpht U.S. Aclear Regulatory Commission Licensing 8 Safeguards tagineer tenshington. 9.C.

20655 northease utilities service Co.

P.O. tot 270 nr. Robert staker Mertford. CT M101 P.O. Boa 378 t

Germe ntsen,10 30B74 huc1eer Safety Analysis Center

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Electric Tower Research Institute Ier. Charles M. Rice Mll Millelem Avenue 5

955 toest leth Street P.O. Sea 10412 '

Ideho Falls. 10 SM01 Polo Alto. CA 94303 i

,.,.-i Dr. Ralph E. Lapp IIPO Records Center NDMb A

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t.1CENSEE EVENT REPORT

' CONTROL BLOCK:

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,v EVENT DESCRIPTION ANb PROB ABLE CONSEQUENCES h tene. ehe ATue non.1 papotn 1

o 121 l On 3/10/83, during an ATWS channel surveillance 01311 11ghts showed a half trip when no trip signal was being, applied.

A voluntary I

'o la 1 L14 day tco was entered to investigate this apparent f ault. Durinc 'this' time.

I This 1

o 151 L.the redundant ATwS channel and other T.S. reautred systems were coerable.

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o 161 l event caused no threat to the niih14 e heni t h and enfety.

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89 COMP.

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$YSTE M CAust CAUSE CODE Coot Suso>Of CouPONENT CODE SueCoDE SueCO-)f l Il Alh [Bjh (Bjh l Il NI SI Tl Rl Ujh ('zjh >(z_j h o19]

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10 11 12 13 18 19 20 Sf OUR NTI AL OCCUR RINCE

' REPORT RIVi$loN No.

,. tin /Ro tytNT YE AR

. REPORT No.,

Co0E TYPE l -0 l 17 kE l8l3l

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CAUSE DESf:RIPTION AND CORRECT 1VE ACTIONS h l1Io1lThe neon indicator lichts used in the trio'circuita have been foimd en he mencitive 1 111 l to spurious voltages thereby giving an erroneous trip indication. A chance to the._,_l 1

g l ATWS functional test (8.M.1-2,9) h,as been made to allow a voltmeter to be used i

iI3l lduring the test to remove the reliance on the neon lichts. A reauest'for engineering nrnvide a mnre nnnitive civetiir mentite hae been in4e4mded, 1 1 l suooort fne n desiew change en 1

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ae NAN oTHanSTATus' @$[sEoN R$

DISCOVERY DESCMIPTaoN h sPowsm NA l

l Surveillance test l

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CONTROL COPY RECORD 1 PC A $ 6 e

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April 13. 1983 ty g nog a B F.ro Ltr. 83-89 N

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Y *bl h/I kef.' &&

Regional Administrator, 34g10n 1 U. S. Nuclear Regulatory Comaission eO m@

631 Park Avenue

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King of Prussia. FA > 19406 M g. -

Docket Number 50-293 I.icense DPR-35 (LM g-l 3Z01135 s

""'Si" mas comma s:

_s The attached Licensee Event Report 83-013/01T " Field Breaker for "A" '

l Recirculatica Furp HC Set" is hereby submitted in accordance trith the requirements of Pilgria Nuclear Power Station Technical Specification 6.9.8.1.1.

If there are any questions on this subject please contact us.

i Reapeetfully submitted..

O W. D. Rarrington i

Senior Vice P. resident Lia Olsni e ls W Co.)

j Huclear i

Messrs. W. D. Harrington Ms. K. Calderone GCV:dap !

J. E. Hmmard NOO Licensing (Jack Fultan)

J. M. Ea11entine PNPS Records Center supervist l

Enclosure:

15.1 8}-013/01T-0 W. J. Armstrong

< IstC Resident Inspector i

H. F. trannan C.J.M. Lettertoot for Ltas R. M. Sutter cc: Document Control Desk P. A. Foulsham

{' j g., g. It p.

U. S. Nuclear Regulatory Commission P. f. Giardielte 8- [ g"c*9h Washington. D. C.

20555 g

A. V. Morisi Standard Brto LER Distribution J. W. ulcholson D" E 4 A. L. Onsen RELEASED

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C. K. Regan L. D. Lcker i

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G. C. m itney E. Z. Zimmenski ort SITI D15ftitVTION Dnciament Control Desk st, J. R. Hismulericht U.S. A c1N r Regulatory Commission Licensing 8 Safeguards tagineer tenshingten. D.C.

20555 9

@ f' g }f northeast Utilities Service Co.

p P.O. Sea 270 st Robert staker Martford. CT 06101 P.O. Boa 378 c,

Jg' sersentaman, le 20874 beleer Safety Analysis Center

,s Electric Teser Research Institut.

O se-' Charles R. Rica 3412 Hillview Areense -

U 355 toest 14th Street P.O. Das 10412 Idaho Falls. !D &Mol Palo Alto. CA 94303 r

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7 Dr. 241pn f. Lapp IuPO Rxerds Center 7715 Part Terrace Drive sul te -1500 Alsamadria. WA 22307 1100 Circle 75 Partey Atlante. GA 30339 w~

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_. _ _ _ _ - - - --umv CUtSLA*hG 1.lCENSEE EVENT REPORT cOurnOL stOco l I

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(PLEASE PRINT OR TYPE ALL KEQUMED INFOT.uAT80NI e

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.0 si DoCxETNUM.ER se se EVENT DATE M

M REPOR T 0 ATE 40 j

EVDU DESCRIPTION AND PROB A8LE CONSEQUENCES h lo l 2 l pn 4/3/83, during shutdown conditions the field breaker for the "B" recirc-nnen I

l 8

1 t o t a l ft/G set did' not trip while being removed from service for maintenance.

ThiR l

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IoI*Ilbreaker iR nnte nf Pho A'fW: (:yetam and had it been activated while in the run l

1o I s I imode, it might not have provided its intended function.

This event crented nn i

l o 161 lthreat to the public' health and,, safety.

Thn NR r m e nneffinA via ENS.

Tha l

i l o ) 71 lbreaker is a CE type AK-F-2-25 No. 224A3510-43.

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CODE CODE

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SUSCODE SU8 CODE Fo i s i, Ic 18 l@ l tl@ lJ@ [t y lTlninlvl@ U @ U @

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$f 0 VENTI AL oCCVR R E NCE REPORT REVISION LE R EVENT YE AR REPORT NO.

CODE TYPE NO.

O ajg/R0 18 l i l L-J La l i l 31 1-1 I nli I LT_J I-I' LaJ N

_2) 22 23 24 26 27 N

W 30 31 32 A EN AC ON P

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~CAUSE DESCRIPTION AND CORRECT

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7 IVE ACTIONS h 11101 LThe cause was a bound uo mechanim nrevoneino,the breaker from ooeninc.

Tha "h"

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l3 liyl contact did not open which kept the trip coil energized and caused 1ts failure.

Thel

,i i23 1 breaker was removed, the linkages lubricated with a non-greasy lubricant, both of I

Ii I 3 I l the coils were replaced (the secored due to its close proximity to the failed coil) i l i l A l l and, af ter NRC concurrence with actions taken, returned to service.

l.

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4 9 80 ST

% POWER oTHER ST ATUS DISCO RY DISCOVE RY DE SCRIPTION i

Ii 15 I (_G_j@ l 0 l 0 l 0 l@l N/A l

LAj @ L..., Operational event l

ACTIVITY CO TENT 8:ELEASED OF RELE a3E AMOUNT OF ACTIVITY lil6l Wh dl LOC ATIC*10F RE LE A55 N/A l

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N /A l

7 8 9 to 11 A4 A5 PERSONNEL EXPOSURES 03 NUHsER TYPE DESCRirTtoN ITFi l 01 ol o@l ZI@l N/A I

rERsoNNE'L i.uv' lits oEsCRirTiONh NUueE R E l 0 l 0 l Ol@[

N/A l

7 8 9 11 12 LOis OF OR oAMAGE TO FACILITY 80 TYPE DE SC RirTION

[,,Z_j@l N/A I

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Pust tCtTY 80 8 9 10 ts3UED DE SCRirTIOed N R C USE ON L ",

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8 9 to 68 69 8N G. G. Whitney (617) 746-7900 o

l NAME OF PREPARER PHONE:

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,i' BOSTON EDISON COMP.tNY s

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., PILGRIM NUCI. EAR POWER $*thTION _

l DOCKET No.'.S0-2 QR l

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Attachment to LEC "3-U13N.YM-0

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sCause and Corrective Action:

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l When investigated the breaker was found as f ollows:

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1. ' The main contacts were partially tripped and bound up indicating that a trip signal had been sent to the breaker.

.o g

2.

The shunt trip device had a failed trip coil and the mechanism.

was partially in trip.

3.

The breaker bould not mechanically trip via the mechanical push button.

l Immediate Corrective Action Taken:

1.

The breaker was reuoved from the cubicle, e.rc chutes rerreved, and the trip latch mechanism manually pushed.

Phase one, two and three then tripped.

r

- I 2.

The main and shunt trip linkage'was lubricated with "LPS" penetrating oil ( a non-greasy lubricant).

The breaker was cycled approximately twenty times and then reinstalled.

3.

Applicable sections of the Technical Manual were consulted and specified actions taken.

4.

The redundant "A" M/G set breaker was operated and no signs of similar binding were found.

6 5.

An ORC meeting was held to review the event.. While no root cause could be determined at that time, the ORC agreed that proper immediate i

corrective action had been taken and sufficient testing of the breaker operations had been done. Reactor startup then continued and the plant was critical on 4/3/83. -

6.

The General Electric Company has been contacted to assist in the resolution of'the problem.

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