ML20129A957

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Informs That Region III Will Not Conduct Public Meetings Concerning 850410 Events Re Rupture of Oa Boric Acid Evaporator Rupture Disk & Reactor Trip Caused by Drop of Four Control Rods.Events Will Be Documented in Future Rept
ML20129A957
Person / Time
Site: Byron Constellation icon.png
Issue date: 05/17/1985
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Mccaffrey J, Samelson A
ILLINOIS, STATE OF
Shared Package
ML20129A963 List:
References
NUDOCS 8506050041
Download: ML20129A957 (9)
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Text

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s ff,%,s u~,n o s1 m s NUCLEAR REGULATORY COMMtsslON mS

[ )p ' E REGION lil 5 (g ' s [,- 'f 799 ROOSEVELT RO AD

, , cLEN ELLYN. ILUNOIS 60137 MAY 171985 ,

Docket No. 50-454 Mr. Allen Samelson Assistant Attorney General ,

Office of the Attorney General -

500 South Second Street Springfield, IL 62706 Mr. John McCaffrey, Chief ]

Public Utilities Division i Office of the Attorney General ,

l 160 North LaSalle Street Chicago, IL 60601 Gentlemen:

In your letter dated April 15, 1985, you expressed a desire to receive direct and prompt notice of any public meetings or proceedings that may arise from

- the two events that occurred on or about April 10, 1985, at the Byron facility. Additionally, you requested to be provided copies of any records or i

other documentation generated by or submitted to the U. S. Nuclear Regulatory l Commission regarding the particular events.

i The first event involved the rupture of the 0A Boric Acid Evaporator

. Rupture Disk, which resulted in personnel contamination of five individuals and evacuation of approximately 350 personnel from the Auxiliary Building, Level 346'. Region III conducted a preliminary review of the event and did not consider the event to be radiologically significant. This conclusion was based upon the low levels of radiation exposure, levels of personnel contamination and the particular isotopes involved. . Additionally, all personnel and clothing were readily decontaminated and released, no one received internal contamination, and the level of off-site release was very i low. Therefore, Region III did not and does not intend to conduct any public l meetings or proceedings regarding this matter. However, Region III will document its review of the event in a future inspection report. Attachment 1 is a licensee document which has been provided to the NRC regarding the event.

l Additionally, when Region III issues the inspection report which documents the results of the NRC review, it will be forwarded to your office.

The second event involved a reactor trip after a group of four control rods dropped into the reactor. This same group of four rods had dropped into the reactor on a previous occasion on March 29, 1985. Region III has reviewed the cause of this event and determined that it had minor safety significance.

Although it is undesirable to have rods drop into the reactor, this is not an unsafe condition when all safety systems function normally, as they did in 0041 850517 fDR ADOCM

' S 05000454 PDR

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$:NNre"y MAY 171985 this case, shutting down the reactor. Interim measures have been taken by the

' licensee to provide further assurance that such events will not occur or will be minimized. The licensee is pursuing a permanent modification to the affected system, with the system designer (Westinghouse), and will make any necessary modifications before the affected portion of the system is returned to operation. In view of the significance of this event, Region III does not intend to conduct any public meetings or proceedings regarding this matter.

However, Region III will document its review of the event in a future inspection

-report. Attachment 2 is the NRC Preliminary Notification of Event or Occurrence

. issued by Region III regarding the event. Attachment 3 is the licensee's documentation which has been provided to the NRC regarding the event. When Region III issues the ' inspection report which documents the results of the NRC review, the report will be forwarded to your office.

If we can be of further assistance, please let us know.

Sincerely, l'ortninni $tened by C.E. !!orellS3 James G. Keppler Regional Administrator-

Enclosures:

1. Initial Deviation Report
2. PN0-III-85-33
3. Reactor Trip Root Cause Determination

'cc w/ enclosures:

D. L. Farrar, Director of Nuclear Licensing V. I. Schlosser, Project Manager Gunner Sorensen, Site Project Superintendent R. E. Querio, Station Superintendent DMB/ Document Control Desk (RIDS)

Resident Inspector, RIII Byron Resident Inspector, RIII

'Braidwood-Phyllis Dunton, Attorney General's Office, Envircnmental Control Division D. W. Cassel..dr., Esq.

-Diane Chavez, DAARE/ SAFE W. Paton, ELD L. Olshan, NRR LPM H. S. Taylor, Quality Assurance Division RIII RIII RIII R RIII RIII i afiben*$hI, f P %& -

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SEPCATASLE EbENT NOTIFICAT10N 20 OAv PEPORTABLE/10CFR,,,,,,,,, . REGICN III DATE TIME 5 Cav REPORT PER 10CFR21 NSO OATE T l a.(

] ANNiAL'SPECIAL REPORT REQulRED CECO CORPORATE NOTIFICATION MADE 4F A8OVE NOTIFICATION IS PER 10CFR21 A.l,R. s. ..........

TEMPY L.E.R. ., CECO CORPORATE OFFICER 6 ATE T'ME

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INVESTIGATICN REPORT & RESOLufl0N ACCEPTED BY STATION Review

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Jasnepers Returned & Tracking Les completed: Date Reviewed by Elft Engineer Date

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APPROVED NOV 031984 1

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BAP 300-1 Revision 5 B. O. S. R.-

ENGINEERING REVIEW CHECKLIST p- /

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1. Could the alteration affect the seismic capability of a seismic class I component? ,

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2. Could the alteration possibly alter the environmental qualification of any component required post-accident?

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3. Will the alteration be made to safety actuation systems within the Protection portion of the channel?

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!~ 4. Could the alteration affect fire doors, fire related '

O E H assy's, deluge / foam systems. CO2/Halon system. l fire pumps or hose stations?

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5. Could the alteration affect more than one train of 0 30 i components?

i I 6. Will the alteration .r Aucj the performance characteristic 0 MD I of any safety-relat<A conponent?

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7. Could theialteration increase the electrical loadina of a safety-related electrical system?

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,,A4 A-Will the alteration increase the potential for equipment dg?

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2. 4 If any are marked YES. a written engineering review is required.

I B. SAFETY EVALUATION CHECKLIST Does the Temporary System change increase the probability of i occurrence or consequences of an accident or malfunction of ,

equipment important to safety? . . . . . . . . . . . . . . . . . . . YES 0 NO O Does the Temporary System Change create the possibility for an accident or malfunction of a different type than any

. evaluated previously in the SAR? . . . . . . . . . . . . . . . . . . YES 0 g0 Does the Temporary System Change reduce the margin of safety as defined in the basis for any Technical ,

Specifications.? . . . . . . . . . . . . . . . . . . . . . . . . . . . YES O NG G Bas s for Determination Puhon sf jord-, ir us/ Rfet'L n)5 Thu a iw r#f d tv Tnf,4 rte er FJ,1x 4d /

w If any are marked YES. NRC approval is required.

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'C2 RADATION RELEASr COLUMN 1: Byron Unit 1 ,

COLUMN 2: Telecon from Resident Inspector COLUMN 3:

a At 1307 CST 04/10/85 licensee started. venting the Volume Control Tank to the Waste Gas System. Due to a temporary alteration installed around a vent line check valve, the OA (Boric A,cid Evaporator was over pressuri:ed causing a rupture disk to burst.

The contents of the evaporator flashed to steam and vented to a floor drain in the auxiliary building. At 1345 area radiation alarms were activated. Auxiliary building vent fans were started and the area evacuated. No detectible radiation activity was released off-site. Following decontamination workers were whole body counted. Whole body counts showed that no ingestion of radioactive material had occurred.

COLUMN 4: Resident Inspectors followup per MC 2515.

s 4

PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENL.t-Mill-bo-as uate sprii 44, nos This preliminary n::tificaticn constitute? EARLY nstice of ovents of POSSIBLE safety or Nb

  • public interest significance. The information is as initially received without veri-

. fication or evaluation, and is basically all that is known by the staff on this date.

Facility: Comonwealth Edison Co. Licensee Emergency Classification:

Byron Nuclear Plant, Unit 1 Notification of an Unusual Event Byron, IL 61010 Alert Site Area Emergency Docket No: 50-454 General Emergency

. XX Not Applicable Subj;ct: MEDIA INTEREST IN REACTOR SHUTDOWN AND UNRELATED CONTAMINATION INCIDENT At 1:35 p.m. on. April 10, 1985, the reactor tripped after a group of four control rods dropped into the reactor. The plant had been perfonning testing at 30 per cent power. All '

safsty systems functioned normally.

The same group of four reds had dropped into the reactor in a previous incident on March 29, 1985. That incident was attributed to a fuse problem. The licensee is inv:stigating the cause of the most recent occurrence, and the Resident Inspectors are monitoring the investigation.

Shor1.ly after the reactor shutdown, a contamination incident occurred in the Unit 1 auxiliary building. Five workers received low levels of clothing and skin contamination, and abaut 300 workers were evacuated from the building.

The contamination occurred when a rupture disk on an evaporator leaked due to a temporary piping modification which allowed excessive pressure on the rupture disk. Contaminated water and team entered the auxiliary building. The affected workers received contamination on their shoes, clothing, and skin. They were successfully decontaminated, by showering, and a sub:.aquent whole body count showed no evidence of any internal deposition of radioactive material.

The Resident Inspectors and Region III radiation specialists are following the licensee's activities. The licensee notified local news media of the two events, and there was ext:nsive news media interest in the Rockford and Chicago areas. Region III (Chicago) has resp:nded to inquiries.

Tha State of Illinois will be notified.

R:gion III was notified of the control rod problem by the Headquarters Duty Officer at ,

2:25 p.m. on April 10, 1985. The contr.mination problem was not reportable, but Region III ]

learned of it from a member of the public at 4:30.p.m., April 10, 1985. This infonnation is curr:nt as of 2:30 m., April 11 1985. l nTFW  !

CONTACT: y . er R.'Warnick l FTS 388-5590 FTS 388-5644 FTS 388-5575 l

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1 DISTRIBUTI0N:

H. St.M- MNBBQ AQ Phillips4 G 9 E/W,q:5] W111ste h O'? i Chairman Palladino ED0 NRR IE . NMSS Com. Roberts PA OIA RES Com. Asselstine MPA AEOD '

Com. Bernthal ELD Air Rights _Q:M, MAIL:

INP0M:06 ADM:DMB Com. Zech SP DOT: Trans Only SECY NSAC z si(

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%fdN31 - . . _ , __ . ._. _ _- _ _ . _ _ _ _ _ _ _

Rev. 07/06/84

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RADIATION OCCURRENCE REPORT Date - @ Time: /3 30 Type of Occurrence: f, R. o. R. NO. : sr-cos (See Reverse)

PERSONNEL INVOLVED "

NAME SSN FILM BADGE /TLD# COMPANY

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Location:

3bb M j J Description of Occurrence (Include all Significant Information):

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OCCURRENCE REPORTED TO:

Estimate of Exposure Recei ed: TITLE NAME _, DATE/ TIME External: N/N/*4 e N/Mk 7. k. M I/tt/f,/<,,oo Internal: g ,.,, , g References (RWP No. , Survey Report, etc. ):

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C.E.CO. 46 2537 3 42

TYPE 3 0F OCCURRENCES External Dose Contrel Ad91ntstrative Controls 1 Improperly posted or controlled radiation area or 10 Personnel in a controlled area without adequate high radiation area. or required timexeeping, monitoring, or dosimetry.

2. Discovery of working dose rates to a worker inside 11. Pefsonnel in a controlled area without required a controlled area that significantly exceed the training. a expected dose rate.
12. Personnel in a controlled area without adequate 3 Any p# sonnel external dose equivalent in excess protective equipment.

of the 10 CFR 20 limits.

13. Personnel in a controlled area it;roperly ustr4
4. Any in-plant personnel whole body dose equivalent required protective equipment, that exceeds the dose authorized by Radiation-Chemistry or the administrative contrcls 14. Personnel practice in a controlled area in established in the Radiation Protection Standards. violation of the Radiation Protection Standards.

Radiation Protection Procedures, facility

~ Int'rnal Dose and Surface Contamination Control Technical Specifications. or other regulatory requirements.

F'  ::Xin or personal clothing contamination greater than 1 mR/hr above background as measured with Noncategorized an aDproved beta-gama instrument.

15. It is believed that a violation of regulatory
6. Exposure of personnel to concentrations of airborne requirements pertaining to the protecticn of radioactive material resulting in an internal individuals against radiation has occurred.

deposition 3r. excess of regulatory requirements.

16. A significant action or situation inconsistent

,. Any case of poattive nasal surveys in excess of with the A1. ARA philosophy is observed.

10.000 dom.

17. Other (specify).

8 Spread of significant contamination in the tretediate work area beyond that which was planned or might ncrmally be expected.

9. Spread of significant contamination outside of a controlled area.

adiation-Chemistry Follow-Up: Date: (,/ M -1 f Signed: h -

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i fipril 10, 1985 URE-PRO 22A (Aux. Oldg. Enhaust OD - particulate thannel) liigh Alarm Setpoint = 7.62E-09 Alert Alarm Setpoint = 3. 81 E--09 limg pgt.egtgt Bggding Jyg1/gg1 ghetyg 1300 1.85E-11 Normal 1310 1.85E-11 Normal 1315 9.89E-03 High Rad 1320 1.42E-07 High Rad 1330 1.54E-07 liigh Rad 1340 3.50E-08 High Rad 1350 4.04E-08 High Rad 1359 Aux. Bldg. Exhaust and Supply F'an tur ned on.

1400 4.20E-08 High Rad 1410 3.42E-OB High Rad 1420 1. 73E- 08 High Rad 1422 (ieturn ta norm) 1.05E-10 Normal

. 1430 2.78E-10 Normal ORE-PRO 22D ( fiux . Lldg. Exhaust OB qas channel)

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April 10, 1985 ORE-PRO 13A (Gan Decay Tan.k Cubicle particulate chgnnel)

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'1440 1.02E-09 Normal 1450 2.69E-10 Normal 1500 2.69E Normal f

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- April.10, 1985~

1RE-PRO 28B (Aux. .D1dg. Vent Stack Effluent - gas)

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~

High Alarm Setpoint = 3.12E-03 c Alert Alarm Setpoint = 3.12E-04 s

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~

PRELIMINARY NOTIFICATION OF EVENT OR' UNUSUAL OCCURRENCE--PNO-III-85-33 Datehf1"b,"19$5 This preliminary notification constitutes EARLY notice of events of.POSSIBLE safety or public interest significance. The information is as initially received without veri-

! fication or evaluation, and is basically all that is known by the staff on this date. .

l Facility: Comonwealth Edison Co. Licensee Emergency Classification:

l Byron Nuclear Plant, Unit 1 Notification of an Unusual Event I Byron, IL 61010 Alert

! Site Area Emergency Docket No: 50-454 General Emergency XX Not Applicable j

Subject:

MEDIA INTEREST IN REACTOR SHUTDOWN AND UNRELATED CONTAMINATION INCIDENT l At 1:35 p.m. on April 10, 1985, the reactor tripped after a group of four control rods l dropped into the reactor. The plant had been performing testing at 30 per cent power. All safety systems functioned normally, i Th2 same group of four rods had dropped into the reactor in a previous incident on l March 29, 1985. That incident was attributed to a fuse problem. The licensee is investigating the cause of the most recent occurrence, and the Resident Inspectors are i monitoring the investigation.

Shortly after the reactor shutdown, a contamination incident occurred in the Unit I auxiliary building. Five workers received low levels of clothing and skin contamination, and about 300 workers were evacuated from the building.

The contamination occurred when a rupture disk on an evaporator leaked due to a temporary piping modification which allowed excessive pressure on the rupture disk. Contaminated water I and steam entered the auxiliary building. The affected workers received contamination on

' their shoes, clothing, and skin. They were successfully decontaminated, by showering, and a subsequent whole body-count showed no evidence of any internal deposition of radioactive material. .

The Resident Inspectors and Region III radiation specialists are following the licensee's activities. The licensee notified local news media of the two events, and there was extensive news media interest in the Rockford and Chicago areas. Region III (Chicago) has responded to inquiries.

j The State of Illinois will be notified.

l Region Ill was notified of the control rod problem by the Headquarters Duty Officer at 2:25 p.m. on April 10, 1985. The contamination problem was not reportable, but Region III learned of it from a member of the public at 4:30 p.m., April 10, 1985. This information is current as of 2:30 m., April 11, 1985.

y

'f fiNO CONTACT: . r ger R. Warnick FTS 388-5590 FTS 388-5644 FTS 388-5575 DISTRIBUTION:

H. St. J)l6-1 MNBBLlA9 Phil'ips4 GCl E/W9:5}

f WillsteA O)

Chairman Palladino ED0 NRR IE NMSS Comm. Roberts PA OIA RES Com. Asselstine MPA AE0D Com. Bernthal ELD Air Rights 4:% MAIL:

Com. Zech SP INP0d:O(3 ADM:DMB SECY NSAC3. gg DOT: Trans Only ACRS '

, CA A PDR Regions 13:lQ ,IIM)pplicable

, IV8:Resident 4, VA:Ag Site 4% Licensee (Corporate Office)45N1

  • Dav. 07/06/84 l
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