05000387/LER-1986-001, :on 860110,two Divs of Control Room Emergency Outside Air Supply Sys Declared Inoperable Resulting in Four Dampers Not Being Tested.Caused by Procedure Deficiency. Dampers Tested.Procedures Will Be Reviewed

:on 860110,two Divs of Control Room Emergency Outside Air Supply Sys Declared Inoperable Resulting in Four Dampers Not Being Tested.Caused by Procedure Deficiency. Dampers Tested.Procedures Will Be Reviewed

ML20137W096
Person / Time
Site:	Susquehanna
Issue date:	02/07/1986
From:	Crimmins T, Hirt J PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-86-001, LER-86-1, PLIS-145, NUDOCS 8602200055
Download: ML20137W096 (5)

LER-1986-001, on 860110,two Divs of Control Room Emergency Outside Air Supply Sys Declared Inoperable Resulting in Four Dampers Not Being Tested.Caused by Procedure Deficiency. Dampers Tested.Procedures Will Be Reviewed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(1)
3871986001R00 - NRC Website

text

N8ic F.r. Joe u s NuCLtJJi ktt uLATORY CommsesseOfs AwAO*tEO Oue seO sigo_cios LICENSEE EVENT REPORT (LER)

*"'8"

FACILITY Naast np OOCKET 8eue8SSR (2)

PAGE 01 Susquehanna Steam Electric Station - Unit 1 ol5l0l0lol31817 1l0Fl014 TITLE te Four Isolation Dampers Not Adequately Tested.

EVtNT DAf t 155 LER asunsetR tel NEPORT OAff (7)

OTHER F ACILITiES INv0LvtO (0)

WNTH DAY vtAR vtAR

%C$$Ab 7,$,

MONTM OAV VEAR

1. Acskevy MAwes I DOCKEY Nuwetniss SSES - Unit 2 o I 5 I o I o I o I 31818 0l1 1l0 8

6 8l 6

~

0 l 0l1 0l0 0l2 0l7 8l6 o is,o g o, o, ; i Twis REPORT is svensiTTt0 PuneuANT TO TMs siEOuiREnsENTs Oc to CrR I iCa e

.,,.., ene a es siti R800E ml 2

20.402(bl 20 405 4)

SS 734sn2ntet 73 F1(b)

PourtR 30 40Si.ninti to 384.nti 30 F34sn2n.,

73.714 1 1I0 t 0 noaamnium semai a rm nan.n OTHER,, -

A -,

1.

• • I,*"*'"""*""

7

/.

no..amnimi minnaini m,m nen nA

[

mninNi

=>mian.,

m,mian.e.n.)

3 n,1.,

......u.,

....,1.,

LICENSEE CONTACT FOR THIS LER nti NAME TELEPMONE NupetR Jeffrey A. Hirt - Engineer Level I 71117 514121-13191117 ComePLEft ONE LINE FOR BACH COnaPONENT P AltuRE Of 0CRISED las THIS AGPORT 1933 Wa's[ AC<

R$ R,T,AggLE

" yN AC.

N R

RTAs jq

CAUSE

SYSTEW COMPONENT

CAUSE

sytTEM CourONENT y

p,pw l

I I I I I I I

I 1 !

l ! I I

I I I I I I I

I I I I I I SUPPLEMENTAL REPORT EXPSCTED (144 WONTM OAV YEAR

.u...,0 4 7,Si r,,, -,

w,ef,0,U,.,,,04 Omi aO i

i l

A=T R AeT,v-.,,..a

.,-, n.)

On January 10, 1986 both Unit 1 and Unit 2 entered Limiting Condition for Operation (LCO) 3.0.3 because the two divisions of the Control Pocn Emergency Outside Air Supply Systen (CREGASS) were declared inoperable due to a surveillance procedure deficiency. S0-030-002 "18 Month Control Structure Ventilation System Operability Test" did not test four isolation dampers to close within eight (8) seconds after receipt of a high chlorine test signal.

This is required by Technical Specification (T/S) Surveillance Requirement 4.7.2.d.2.

The four isolation dampers were satisfactorily tested to close within eight (8) seconds and Ifo 3.0.3 was cleared seventy (70) minutes after it was entered. Both Units continued 1001, power operation throughout the event.

A review of a selected number of surveillance procedures will be conducted to determine if a full investigation of all surveillance procedures is warranted.

The review will consist of an operational scoping of the systerns covered by the selected procedures to verify that all T/S requirements are satisfied.

Prior to this event an addition to an administrative procedure had recently been issued which stresses that new, renewed and revised surveillance procedures be examined carefully to make certain that they conform to and satisfy all T/S requirements. S0-030-002 had not yet been reviewd under this revised administrative procedure.

J (.) )

8602200055 860207 PDR ADOCK 05000307

/ / ;

9 PDR RC.. n.

es ul

a ~

NRC form 3sSA U $ NUCLEAR KEGULATOCtY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Arenovfo oue No sino-oio4 Exe.aEs acauss F ActLITY NAME (18 DOCKtT NUMaER til LER NUM8ER ISI PAGE131 "O

000 Susque11 anna Stean Electric Station

"^"

Unit 1 01510 l 0 l 0 l 3 l 8 l 7 8l6 -01011 0 10 0 l2 OF 0l4 TEXT HF more apece e roeuwed was edssoner %#C Form 356A s1(in On January 10, 1986 while both Unit 1 and Unit 2 were operating at 100% the two divisions of the Control Rom anergency outside Air Supply System (CREQASS) (BH) were declared inoperable as a result of a surveillance deficiency. This caused both Unit 1 and Unit 2 to enter into the ' motherhood clause' of Technical Specifications (T/S); otherwise known as T buiting Condition for Operation (ILD) 3.0.3.

In a review of SO-030-002 "18 Month Control Structure Ventilation System (VI)

Operability Test" the NRC Resident Inspector discovered the surveillance procedure does not fulfill the requirments of T/S Surveillance Requi snent 4.7.2.d.2.

The surveillance requirment states:

Each control rom mergency outside air supply subsystm shall be demonstrated OPERABLE at least once per 18 months by verifying that on each of the below isolation mode actuation test signals, the subsystm autmatically switches to the isolation mode of operation and the isolation dampers (OMI) alose within 8 seconds:

a)

Outside air intake chlorine-high b)

Outside air intake radiation-high c)

Reactor Building (NG) isolation The attached diagram shows a simplified flow path of CREGASS. Normal air flow to the control structure heating and ventilation systm is through the two HD-07802 dampers. On a high radiation or Reactor Building isolation signal these dampers close and the follcsing dampers open:

IID-07814A HD-07813A HD-07814B HD-07813B HD-07812A IID-07811A HD-07812B HD-07811B This rxxic of operation filters the outside air before it is delivered to the control structure heating and ventilation system. Because the filter units can not rcrnove chlorine the HD-07812 and HD-07814 dampers close in addition to the HD-07802 dampers on a high chlorine signal. 'Ihis puts the control rom in a recirculation mode of operation.

In S0-030-002 the HD-07812 and HD-07814 dampers were verified to open on a high radiatior and Reactor Building isolation test signal; however they were not timed to close on a high chlorine test signal. Thus if a high radiation signal or Reactor Building isolation signal were received and then followed by a high chlorine signal it was not known if the HD-07812 and HD-07814 dampers would close in eight (8) seconds.

Ifo 3.0.3 was entered at 1145 on January 10, 1986 and cleared at 1255 on the same day after the four dampers (HD-07812A, HD-07812B, IID-07814A, and HD-07814B) were tested to close within eight (8) seconds after a high chlorine test signal.

3,oMm..

s

NRC Form Je4A U 5 NUCLEAR KEGULATO2V COMMI55 SON LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A,*aovEo oue so mo-oio4 E.,,R E s. #.,

e FACILITY NAME 113 OOCK E T NUMBER 12) ggg q.fMSERf6)

PAGE135 Susquehanna Steam Electric Station

" MW.

I D*.O Unit 1 0l51010l01318l7 816 0 l 0l 1 01 0 013 0F 0h TI.XT 177 more space e --

_, ese _ _. _ MC Forme J8E4's> I171 Corrective Actions To Prevent Recurrence:

A review of a selected number of surveillance procedures will be conducted to determine if a full investigation of all surveillance procedures is warranted.

'Ihe review will consist of an operational scoping of the systan(s) covered by the selected procedures to verify that all T/S requiranents are satisfied.

Prior to this event an addition to an administrative procedure had recently been issued which stresses that new, renewed and rev'3ed surveillance procedures be examined carefully to make certain tha.t they conform to and satisfy all T/S requirements. S0-030-002 had not yet been reviewed under this revised administrative procedure.

i

,.,C,.o....

IL8MdireENC# 00TE8DE Ai(

WLY l

SVSM A S t thC't.ts tEC Ftcol 9fETH i

outsada.

A ida'.

l Air Air l

4-Ho-018tlA 1(D-oTBLaA l

1 C8t,EoAM

/

/

FlLTW.H. 04ft1 d L

[

I l

Ho-C't93^} [

HDd:UBL'4A J

f i

J f

HomBs46

[ HD-OMib l

umasaa

/

5

_A ru. Tea, og res C. REDES 1

/

d ' /

( HD-07802 A O

No-o78ttS

/

rno-oist36 u

/

I i

l n

ro co.rmot smocrog Fu co4190L '#mm w u u s.oe, Aig saan.Q HEAnN6 Ado 9ErFitAncri FWoR 000u4 s93EM

- ro codTeot 3YRoc. TORE.

l SYSTEM ComWR HEATW4(r Areo VENTn.ATod j

Re diccA CocLid6r sVSTen CowN Ado comRJrER s4 stem Ae4o coe. rRot 11pc>m M comuws 39 tun $

1 l

litoom dt.cx A cc o u M(a SVSTEM j

Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215 / 770 5151 February 7, 1986 U.S. Nuclear Regulatory Ccumission Document Control Desk washington, DC 20555 SUSQUE!IANNA STEAM ELECIRIC STATION LICENSEE EVDTT REPORT 86-001-00 ER 100450 FILE 841-23 PLIS-145 Docket No.

50-387 License No. NPF-14 Attached is Licensee Event Report 86-001-00. This event was determined reportable per 10CFR50.73(a) (2) (1), in that Unit I and Unit 2 operated in a condition prohibited by the plants Technical Specifications as a result of a deficiency in a surveillance procedure.

{'

/*j

(

l J

(' /

'Q l

Wm/

)

T.M. Crinmins, Jr.

Superintendent of Plant-Susquehanna JAII/pjg cc: Dr. Thanas E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Canission 631 Park Avenue King of Prussia, PA 19406 Mr. R.H. Jacobs Senior Resident Inspector U.S. Nuclear Regulatory Ccrmission P.O. Box 52 Shickshinny, PA 18655 I 6 L t-W