S9 RESUUATORY INFORMATION DISTRIBAUTION SYSTEM (RIDS)

ACCESSION NBR:8011260254 DOC,DATE: 80/11/19 "NOTARIZED: NO FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow AUTHNAME AUTHOR AFFILIATION MINECK,D,,. Iowa Electric Lfight & Power Co. RECIP.,NAME RECIPIENT AFFILIATION KEPPLERJ.G. Region 3, Chicago, Office of the Director

SUBJECT: RO:on 801111preactor vessel excessive cooldown rate in apparent violation of Tech SPec 3.6.A.1,Evaluation determined Tech Specs not violated.Event not reportable,

DISTRIBUTION CODEi: A4002 COPIES RECEIVED:LTR fENCLi SIZE:j1 TITLE: Incident Reports

NOTES:

DOCKET # 05000331

- n a

RECIPIENOT ID CODEVNAME, IPPOLITOT. 04

A/D COmP&STRU06 A/D MATL & WU06 A/D PLANT SYS1O A/D SFTY ASSE12 ACC: EAL BR 14 ASL8P/J:.HARD CHEM ENG 8R 16 CORE PERF SR 18 DIRENGINEERI20 DIR,SYS INTEG22 EQUIP QUAL R25 I&C SYS BR 29 JORDAN,E:./IE; LIC QJAL 3R .31 MECH E'JG $R 33 NRC POR 02 OR ASSESS BR 35 R LA S 8R39

d FILE 01 SFTY-7= EVA42 SYS INTERAC 345

ACTION:

INTERNAL:

EXTERNAL: 46 05

COPIESU T T R 3

LI 1 1 1. 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 L2 1

16 1

ENC II

t !

RECIPIENTO ID CODE/NAMEL'

A/D ENV TECH 07 A/D OP REACT009 A/D RAD) PRO: 11 A/D TECHNOLOG13 AEOD AUX SYS SR 15 CONT SYS BRI 17 D/DIRHUM FAC19 DIRHUM FACI S21 EFF TR SYS BR23, GEOSCIENCES 26 I4E 05 UIC GUID BR 30 MATL ENG BR '32 MPA OP EX EVAL R34 POWER SYS 3R 36 REACT SYS 3R 40 RELU & RISK A 41 STRUCT ENGSBR44

COPIES UTTR ENCL

11 L 1 2. 1 1 1 1 1 1 2 . 1 1 3 3 1 1 1 1

LPDR 03 1 TERA;DOUG MAY. 1

NOV 2 8 1980

TOTAL NUMBER OF COPIES REQJIRED: LTTR

0

ACRS NSIC:

69 ENCL

14

198o NOV 25 PM 2 3 A

.Is HIT t 7--I (AN SERVICES

7iS

Iowa Electric Light and Power Company November 19, 1980

DAEC - 80 - 501

Mr. James G. Keppler, Director Office of Inspection and Enforcement Region III U.S. Nuclear Regulatory Commission Glen Ellyn, IL 60137

. Subject: Reclassification of Reportable Occurrence

File: A-118a, TE-4

Dear Mr. Keppler:

On November 11, 1980, a Prompt Notification of a Reportable Occurrence involving a reactor vessel excessive cooldown rate in apparent violation of Technical Specification 3.6.A.1 was reported to your office. Since then our investigation has determined that Technical Specification 3.6.A.1 was not violated. We have thus reevaluated this event and determined that a reportable condition did not exist and accordingly, no further report will be submitted reference specification 3.6.A.l. We regret any inconvenience this might have caused.

'Daniel L. Mineck Chief Engineer Duane Arnold Energy Center

DLM/n

cc: Director, Management Information and Program Control (2) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

U. S. Nuclear Regulatory Commission C/o Document Management Branch Washington, D. C. 20555

NRC Resident Inspector

6o 1 2 60

Duane Arnold Energv Center * RO. Box 351 * Cedar Rapids, Iowa 52406 319/851-5611

0I

I

Iowa Electric Light and Power Company 2 2 4 November 13, 1980

DAEC-80-499

IONA SERVTCZS

Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S.' Nuclear Regulatory Commission - Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject: Licensee Event Report No. 80-052 (30 day)

File: A-118a

Dear Mr. Keppler:

In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report. (Total of.3 copies transmitted).

Very truly yours,

Daniel L. Mineck Chief Engineer Duane Arnold Energy Center

Docket 50-331

attachment

.DLM/MSR/pl

cc: -Director, Office of Inspection and Enforcement (30) U. S. Nuclear Regulatory Commission oo) Washington, D. C. 20555

Director, Management Information and Program Control (3) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

U. S. Nuclear Regulatory Commission c/o Document Management Branch NOVi Washington, D. C. 20555

NRC Resident Inspector - DAEC

1)uane Arnoid Energv Center * P0. Box 351 * Cedar Rapids, Iowa 52406 * 319/851-5611

NRC FOR

7 8

CONT

7 8

14

7 8

M 388 U. S. NUCLEAR REGULATORY COMMISSJON

LICENSEE EVENT REPORT

CONTROL 8.OCK: (PLEASI PRINT OR TY'S ALL REQUIRED INFORMATION) . 1 6

I IIA IO IA C 1i 0(~ 0l -b0 0o0 0101-I 0I oiO ii11Li111i111 ... J 9 LICENSIE COOE 14 15 LiCENSE NUMEGR 28 LICNS Type j0 57 S8

SOURC" [.j 10 15 10 10 101 313|1K~')Il o1011r i jLatoe It 211112 1 [ol 60 61 00CKET NUMBER 68 69 EVENT OATE 74 7S REPORT OATE 80

EVENT DESCRIPTION ANO PROBABLE. CONSEQUENCES

During surevillance testing the alarm which indicates "ADS Core Spray or

RHR Running" did not clear when initiating signals from RHR pumps were s

ecured. RHR Pump Discharge Pressure Switch (PS-1925B) which provides the I

signal was considered inop. Operability requirements for RHR pump instru

I mentation is outlined in Tech Spec Table 3-2R- RHR pump affpctpd-1P-??9 I

I D-was kept runnina during PS l9?250 inoperability to Pnqurp evetpm lnp r

I eliability. No similar prpvious awagirrncen ncnrAnd 9

SYSTEM CAUSE CAUSA COMp .. VALVE COOD COo SuaCoe COMPCNENT C00 SUSCCOE SUsCoCo

[T JIFe L..@ LFJ @ IT IlLTIR1 W& L. 7 8 9 11 12 13 Is 19 20

SEQUENTIAL OCCURRENCE VPORT REVISION

LEA/0 rEVENTYSAR AEPOAT NO. CO0 lYPs No. PEPORT 181 :j 1@ UQE jy (- 0 1 5 I2 L L-L L,..L.3 ..--- , !,.,,,

L 21 22 24 2a 27 28 29 20 31 32 ACTION FUTURE EFFECT SHUTOOWN ATTACHMENT NPRO-S PqIMe COMp. COMPONENT TAKEN ACTION ON PL.ANT METHOO M4URS SUsMITTE0 FORM tQ8. SUPPLISA -MANUFACTURER

B '@ 3 [ 21 W0 1 010 1 L W LL W 513 18121 33 34 5 38 40 41 42 43 44 47

CAUSE OESCAIPTION ANO CORRECTIVE ACTIONS

to The microswitch was stuck on PS-1925B causing the alarm function to rema.

lin engaged. The microswitch was reset and plunger switch lubricated and

lexercised before PS-1925B was returned to service. PS-1925B is manufac I

i tured by Static-O-Ring model SN-AA3-X95TT. The switch was functionally

1 l tested sat. No further corrective action planned.

FACILITY 0 ETH40 OF STATUS 1POWIR OTHER STATUS CISCOVERY CISCOVERY 06SCRIPTION

[ LEJ@ 10 19 I 9 I NA IL-je Surveillance Test S a 10 12 11 44 5 4 so

ACTIV1TY CNOTENT RLtLEASEO OF A.EASE AMOUNT OF ACTIVITY W 0 NA 0

EIDG1® Z G I Z ( NA ___

7 8 9 10 1 1 45 *IRSONNeL EXPOSURES 'UM8SA TYPE OESCRI PTON 9

17 0 1 0 10I Z | NA 7 8 9 11 12 12

PERSONNEL INJURIES NUMER OESCA!PTiONe

1 lolo0191 NA 7 a 9 It 12

LOSS OF OR OAMAGE TO FACILITY TYve OESCRIPT1ON

|Z I@( NA 7 8 9 10

PUBLICITY NRC USE ONLY ISSUEO oESCRIPTrON

E | N 1 NA 7 a 9 0 63 89 so.

NAME Of PREPARE Matthew S. Rager 319-851-5611

;

01V

Iowa Electric Light and Power Company November 13, 1980

DAEC-80-497

Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission - Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

21 4

Licensee Event Report No. 80-009 UPDATE REPORT (14 day) Previous Report

Date 3-18-80File: A-118a

Dear Mr. Keppler:

In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report. (Total of 3 copies transmitted).

Very truly yours,

Daniel L. Mineck Chief Engineer Duane Arnold Energy Center

Docket 50-331

attachment

DLM/MSR/pl

cc: Director, Office of Inspection and Enforcement (40) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Director, Management Information and Program Control (3) U. S. Nuclear Regulatory Commission Washington, D. C. .20555

S

I/I

U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D. C. 20555

NRC Resident Inspector - DAEC

'NOW~ 1 71 Wg~

Dhune Arnoid Energy Center * PO. Boy 351 * Cedar Rapids, Iowa 52406 * 319/851-5611

NRC FORM 366 U. S. NUCLEAR REGULATORY CCM#MI=SZN (7.77' . LICENSEE EVENT-REPORT ADATE REPORT

"COTRO SLCK: .m m jgWevious Report Date: 3-18-80. CONTROLJ (1L)K PRESSFINT OR TY~i ALL REQUI RED INFORMATlONI

11I A ID JA IC 11 j~~ 01 01 -1 01 0f 010a1 01 -1Int4(1(4 I li 1 1 ,10 7 a 3 UCINSIA coat 14 13. UC3.'iSNUlOeas2 28 UCvI.S1 5" ~ 7 CAT $8

CONIT

01UR [ IL 70 15 ICLO101I3[-3 10 1 3 10b41 81-0 111 12)aLL.L..110JG 7 a 60 6 OOCXrrNUjMSER Q~ 6 EVFMT OATI 74 7s, REPAT OAf so

EV ENT OESCR 11PTION ANO PRO9ASLE CONSEQUENCES©

02IDurinci a refueling-outagie insoection of the main HPCI Dump., a section of

0 ( a split ring was found lodged in-the im eller. Inspection revealed the,

[ split ring piece was from the HPCT booster pump IP-216- Thp remaindpr nf

OS Ithp split ring was not located- This s pl it ring wis iused to position the

SIIP-216 impeller.-The loss of the split ring could have caused damage to

I the pump-thus rendering the HPCI system inoperable. Reference T.S. 3.5.

I D. 1. No' similar even t reports. have-bee n submitted. '1 8 9 0

SYMTM CAUSE CAUSE CU. VALVEcoca CODE SUBCOOG COMPONreT CZOS ^UCC uco

1 Fl® L(3 1 ~ J BI I G 1P I U I M IPI xI& I Bl0 LWi 7. a 9 to I 1 1 UENTIAisAIsS20

SIOUISITIL OCURAFCS EPORT.

aR VEN4TYlEAR REPOAmNO4. coca Type

NU SR 21 22 2 2' 2s 27 -; M 20 31 '

Ac. TOM IJTLIRE EFFMCT St.'UTCOWN , ATTAC.4MENT MAM.S IE QJ. C~PN TAKEN ACTION ON ;L-N? 'JGthO - 4-oups ) SU8MrnrO ED ORM "a8. SUJPR ea ANU.CT'jAER

@ 1.51 819(3 '3 3 6 . 1 04 2 . 42 .6 7

5. 11Improper split ring retent-ion device. The blunt end s et C rews' used to af

rT I fix the shaft 51eeve s pacepr to the -,haft ha~ie heen rpplprimd Ptith Ong pw

Inmt setscrews.. Radingraph, of djnwns.trem pi pi n gfa-iIed to lnr.;tp thp-micc

t'ling sol it rina piece, A GE Safety Review determined that plant safety is......

;~ Iot cmprmisePd hi'h misn it'igpe;. No fut.' corr. ,-action.'

S-.ATUh5 1 ~Pcvvt OTWE S-TATUS oso~Y , .. OSO R

H~ j (5~ 10 10 1'0 lei- NA tC I ( aJ® Refuel in'gOutage Inspection L' 7 a39 10 12 II 4 45 6s

911ELEASEO OFAIMLASE AMCTC%(1 4cr? VITY COZ4TENTOUMT Of AC. IVerY ()N EL4

.m w W I NA_ __ _ __ _ _

.7 3S tO Ii0 46

.4UPAsep TyPE[ OPSCRImTOM @ .> .

1ll0 10 1 01~ NA,''. .. ..

n Ijj~® Nn I .NA 7 a3 9 12 4

ILOSS OF CA AMAGE? TO F. .. ~Y'e OfSCAIPTION7

WOI 71@ NA ,.. ,

7 a39 .. s

P'JBLICITY NCUEOL

7 a 9 10 64 59 so.

NAME 1 OPRIEPAREA Matthew S. Rager PC! 319-851-5611

*NE ARNOLD ENERGY CENTER

Iowa Electric Light and Power Company

LICENSEE EVENT REPORT-Supplemental Data

Docket No. 050-0331

Licensee Event Update Report Date: 11-12-80

Reportable Occurrence No: 80-009

Event Description

At 0800 hours on March 4, 1980 while performing a refueling outage inspection of the main HPCI pump, a section-of split ring was found lodged in the .impeller. The HPCI booster pump was disassembled and it was found that both halves of one of the split rings which position the booster pump .impeller were missing. The split ring and shaft sleeve spacer are used to position the booster pump impeller. The shaft sleeve spacer (which in turn held the split ring in place) was affixed to the pump shaft with blunt end set screws. The set screws had worked out of the-shaft sleeve spacer allowing the shaft sleeve spacer to expand on the pump shaft. The fluid pressure during previous HPCI booster pump operation caused the shaft sleeve spacer to move along the pump shaft uncovering, and thus freeing, the split ring. One half of the split ring was found lodged in the impeller of the main HPCI pump. The missing half of the split ring is a 1/4 inch by 1/4 inch square, semicircular (3-inch inside diameter) ASTM A-276 Type 410 H.T. piece of steel. The split ring/shaft sleeve spacer retainer failure created the potential for the booster pump impeller to thrust and damage itself which would have made the HPCI system inoperable. Reference Technical Specification paragraph 3.5.D.1. The HPCI booster pump, 1P-216, is a Byron Jackson 10 x 10 x 14 , single stage, Type DVS, centrifugal pump. No similar event reports have been submitted.

Cause Description

Improper split ring/shaft sleeve spacer retention device. Thermal expansion allowed the set screws to back out of the shaft sleeve spacer and the shaft sleeve spacer to expand on the HPCI booster pump shaft. The booster pump design is such that the fluid pressure tended to push the shaft sleeve spacer along the pump shaft away from the split ring. Thus the split rirrg was uncovered and free to move.

Corrective Action

The blunt end set screws used to affix the shaft sleeve spacer to the pump shaft h.ave been replaced with dog point set screws which extend 1/16 inch into holes drilled in the pump shaft. This design change accounts for-the thermal expansion of the shaft sleeve spacer and should prevent recurrence of this event. Also review of other Byron Jackson pumps at DAEC indicates that the shaft sleeve spacer is heat shrunk to the pump shaft and that the pump designs are such that the fluid pressure tends to push the shaft sleeve spacer over the split ring. Thus it was concluded that this event is not li.kely to occur in other Byron Jackson pumps at DAEC.

Efforts to locate the missing section of the HPCI booster pump split ring by radiography have been unsuccessful. An investigation by the NSSS vendor determined that the missing split ring piece poses no hazard to fuel or the proper functioning of any primary components. Further the split ring piece will not compromise any safety feature in place at this facility.

No further corrective action concerning this matter is planned at this time.

Page 1 'of 1

v/STRIOUTION 6053

Iowa Electric Light and Power Company NOV 24 P 2 41 November 13, 1980

DAEC-80-496 Dr, u iv7ON SEIRVI CE S

Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission - Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject: Licensee Event Report No. 79-025 UPDATE REPORT (14 day) Previous Report

Date 10-19-79 File: A-118a

Dear Mr. Keppler:

In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report. (Total of 3 copies transmitted).

Very truly yours,

Daniel L. Mineck Chief Engineer Duane Arnold Energy Center

Docket 50-331

attachment

DLM/MSR/pl

cc: Director, Office of Inspection and Enforcement (40) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Director, Management Information and Program Control (3) U. S. Nuclear Regulatory Commission Washington, D. C. .20555

U. S. Nuclear Regulatory Commission c/o Document Management Branch NOW I Washington, D. C. 20555

NRC Resident Inspector - DAEC

tune Arnoid Energv Center * PO. BRo 351 * Cedar Rapids, Iowa 52406 * 319/851-5611

NRC PORIM a UPDATE REPORT -PREVIOUS REPORT DATE U.S& NUCLEAR REGULATORY COMM=S

'77 1-1979LICENSEE EV ENT REPORT

CONTROL BLOCK.: 0jJ (P Q1EAS4E PRINT OR TY'i ALL REQUIRED INFORMATION)

11hA ID JA IC 11 120I 01 0 1-- 010 0! 0! 0Q1 0 1 10 1 0 ® 4 1 i l lei I a 9 LICENSEE CODE 34 I' 15LCtENS1 NUMBER 25 -25 LICENSE TYPE 10 57 CAT 58

CON'T R____~ EPORT 1 51 010 1LIJl01 70 1 SOURCE I L0 j(O1 Ot 1111i(hI 927 197) 111i 12 18 tnoI

7 a 3 1 COCKST NUMBOA 6a 52 EVENT DATE 74 7S REPOAT OATF so

EVENT OIESCRIPT1ON AND PRO8SASLE CONSEQUENCES

o [ While performing an inspection of RHR Piping. seiSmicrestraints GBB-23-S

0=3 IR-158 and GBB-23-SR-160 and pipe hanger GBB-23- H-.152 on the RHR to fuel

75-4 [pool line were found not intact. GBB-23-SR-160 repaired on 10/2/79, AF

FF -l eismic analysis received on 10/5/79 indicated the RHR to fuel p ool line

F0 67 1would rpmain opprahlp diring a QRFr if i ~ ntart The seis;

a7Imic protection of the LPCI system was compromised duiring the period flRR

S123-SR-160 was out of service. Refere-nce T-S.. 3-S-A-3- p aln Pn .77-nlq SYTM CAUSE CAUSE CCPWP. VALVE

CODE COOE SuaSCOll COMPONENT COOS SU4c=O6 suaccci

a 9 to0 1 33 32 13 Is 2AlO SENVEA SPRTO.COOES TYPSCR

21 22 22 24 25 2723 2

ACTION FUTURE. EFFECT? 5I4UTCCWN /\ ASrrAC,4MENT 'NR. PRIME C=.%40 TAK(EN ACTION ON PLANT' .6ETiOO M43UAS SU8MITTEO o~a. SUPPLIER

C.AUSa OESCRIPTICN AND CcRRECT1VE AC-41CNS 27)

~ON

-J

-J

-I -j

~~1

80

-mAN UA c"1 S

S 2 81

* . The restraint damage was apparently

t bove GBB-23-160 was repaired on 10/2

Iipipe welds verified thelintegrity of

32 change. has been developed to install

14e Lf rdm:theUBy~te

ST AT %POE O71,441 STATUS \..

WiG t 1L4J±JGL NA I 3 9 30 12 VI 4

ACTIV31V CONTENT RELEASEDO 0ARELEASE AAMOltNT 010ACnVr

= I @LIz I® NAI I a 9 30 it. 4

SIRSONP4!L EXPOSURES3 .4UP8ER Type OFCAI P7CM

10 IO OIl~lIGI(3 NA . 3 31 32 . 13

P5RSONNItL INJURIES

110 10 10 I NA 7 a39 it 12

LOSS 00 OR OAAMAG9 TO J5ACILIT'Y

I, zlet@ NA 7 a 9 to

PUBLICITY ISUED CESCAIPTiON

T 7a NISLN A 7 a 9 : 0

Caused by a water hiammer. As noted a

179. A UT examx.cnducted on 16i of 2?

teline was not degraded. -A desigin

a vlv t seircitethe affected' 1 I

CISCOVIRY

45 46

'5

30

DISCOVERY SCIT?4)

17necial Tnsn~rtion

LOCATION OF RELLA5~ (~)NA

NAME OF PREPAREp MatthewS. Racier PIN Or~

NRC USE ONLY?

ig 69 so.~ 319-851-5611

30

I:ao

'so"

-A

NE ARNOLD ENERGY CENTER

Iowa Octric Light and Power Company a LICENSEE EVENT REPORT-Supplemental Data

Docket No. 050-0331

Licensee Event Update Report Date: 11-12-80

Reportable Occurrence No: 79-025

EVENT DESCRIPTION

While performing an inspection of RHR piping on September 27, 1979 seismic restraints GBB-23-SR-158 and GBB-23-SR-160 and pipe hanger GBB-23-H-152 on the RHR to fuel pool line were found not intact. An architect engineer seismic analysis was begun on September 28, 1979 to determine if this line would remain operable during a DBE with these restraints out of service. Subsequently, seismic restraint GBB-23-SR-160 was restored to its original configuration on October 2, 1979. The seismic analysis was completed on October 5, 1979 and the results indicated the RHR to fuel pool line would remain operable with GBB-23-SR-160 intact. This occurrence thus compromised the seismic protection of the LPCI system during the period GBB-23-SR-160 was :out of service. Reference Technical Specification Paragraph 3.5.A.3. See also RO Report 77-029.

CAUSE DESCRIPTION

The restraint damage was apparently caused by a water hammer.

CORRECTIVE ACTION

As noted above GBB-23-SR-160 was restored to its 'original configuration on October 2, 1979. A UT examination was conducted on 16 of 22 of the welds on the RHR to fuel pool line. This examination verified that the integrity of the line was not degraded. A design change has been developed to install an additional valve such that this RHR to fuel pool line will be segregated from the balance of the RHR system. This will eliminate the potential for .recurrence of the water hammer problem.

Page 1 of 1

8,)

i)uane Arnoid Enerqy Center * PO. Bov 351 * Cedar Rapids, Iowa 52406 * 319/851-5611

Iowa Electric Light and Power Company

November 13, 1980 DAEC-80-498

Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission - Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject: Licensee Event Report No. 80-051 (30 day)

File: A-118a

Dear Mr. Keppler:

In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report. (Total of.3 copies transmitted).

Very truly yours,

Daniel L. Mineck Chief Engineer Duane Arnold Energy Center

Docket 50-331

attachment

DLM/MSR/pl

cc: Director, Office of Inspection and-Enforcement (30) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Director, Management Information and Program Control (3) U. S. Nuclear Regulatory Commission Washington, D. C. 20555

U. S. Nuclear Regulatory Commission NOVI c/o Document Management Branch Washington, D. C. 20555

NRC Resident Inspector - DAEC

NRC P9ORM 36a t7-m

U. S. NUCLEAR REGULATORY COMMISSON

I

I responsibe to voltage control. The OIG was taken inop for inspection. Te f

I ch Spec 3.8.A.2 requires both djesel agenerators to be operable during re

I actor operation. Required testiha deternined'1f-31 was operable. A 7-day

I LCO was initiated in accordance with Tech Spec 3.5-G.1. 1G-21 was return I

02

05

2 5

'2 I I

I 2 I~ I 7 S

1 Cam switches became loose resulting

1 1 unresponsive to voltace controls. Th

Sijusted and the cam switches were pos

Sility tactpd -6t Rasler Fltrtronic

No further corr. action is planned z 323 FACU~Y(do

STAT1US ocWOTe STATU

7 WO Lol NA ACTIVITY CONTENT

RELEASED OF RELEASE AMOUNT OF ACTIVT

0:!:9 NA 7 a 9 10 1t 44

*SASONNEL EXPCSURES

NUM8AgR TYPE OeSCRIPTICN

0 1 010 ZO(I) NA 83S It 12 13

PIRSONNet. INJURIeS NUM8R OESCMATIONe

1 01 0](1 NA 7 3 9 11 12

LCS OF OR DAMAGE TO XACTUTY YE CESCR'sTON m L2l0I NA

7 8 9 t0 JUSLICITY

SZUED OESCRIPTION

IL I NA 7 a 9 30

NAME OF PREPARES Matthew S. Rager

I ed to service on day 2 to cancel the LCO. No previous similar occurrence

L 9

S.

~~~~~~~1*

s0

REVISION NO.

32

ANU -I

B 1019 1310 BA 7

in the potentiometer motor beinq

e potentiometer motor was voltaSe ad

itioned properly. The DIA was operab

manufaCtrpd affrttd rmpnnnents

at this time.

METWCO 0 CISCOV ERORYR 00CIPTOIC

B113 Surveillance Test 45 46 SO

NA..OCATICN OF RELASE

30

80

30

to NRC USE CNLY

68 59 3o.

;PCNS: 319-851-5611

SYSTEM CAUSE CAUSE . Coup. VALVE COC CCO SiCoce COMPCNENTCC0 SUSCOCE SUsCCOE

IE I El( LLI 0 3 1T1N1 S1 TI RIU 1 ( 1.,IJ (. 79 to it 12 13 IS 19 20

SIQUINTIAL. OCCURRENCE RAfOR 4 EVENT YEAR REPORT NO. COD EYPE

La)0J - 0 1 8 1 o q- I I 1 -o.1 UO L21 2 23 24 25 27 23 29 J. 1 ACTION FUTURE eIECT SJOU1COWN ATTACHMENT 4PRC' APIMECAP. TAKEN ACTICN ON PLANT mETnCO ?4OURS SU6MIT'Eo PQRM,.8. SUPet.'EiR

LWJ@OW LU®J Lz...J lolol oll oi U ® LLJ LAI® 32 34 35 6 3740 st 42 A3

CAuSE 0ESCAIPTICN AND CoRpSC71V ACTTCNS

LICENSEE EVENT REPORT

CONTROL 8LOCK: (PLEASE PRINT OR TYvi ALL REQUIRED INFORMATION) 1 8

{o ] IA 10 IA IC 1 0 0[1 -1020 010 01-10 01Q 4d 11 II 1 O3 7 9 9 UCINSH6 CODE IA 15 UCENSI NUMiaap 25 28 LICEN.SE TYPE JO 57T5

REPORT IL(7)10 15 Q 10 10 131 311 (lei1 10 1141 81 0 1(1 11112 A18 t 0 SOURCE___________ __

7 8 6 S1 GCCKE NUMass Q.89 EVENT DATE 14 75 REORT OATE 30

EVENT OESCRIPTION ANO PROBABt CONSECUENCES G

F5o2 I During surveillance testing of Emerqency Diesel Generators, 1G-21 was un I

I