IR 05000456/1988026

Insp Repts 50-456/88-26 & 50-457/88-26 on 880828-1015. Violations Noted.Major Areas Inspected:Ler Review,Secondary Chemistry Excursion,Startup Test Observation,Operational Safety Verification,Esf & Training Effectiveness

ML20205N042
Person / Time
Site:	Braidwood
Issue date:	10/27/1988
From:	Hinds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20205N024	List: IR 05000456/1988026 ML20205N019 ML20205N035
References
50-456-88-26, 50-457-88-26, NUDOCS 8811030420
Download: ML20205N042 (18)

Text

_ _ _ _ _ -

. .

-

. .

U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report Nos. 50-456/38026 DRP); 50-457/88026(DRP)

Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Licensee: Connonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood Station, Units 1 and 2 Inspection At: Braidwood Site, Braidwood, Illinois Inspection Conducted: August 28 through October 15, 1988 Inspectors: T. M. Tongue T. E. Taylor G. A. VanSickle R. Bocanegra

- .

Q... *

ApprovedBy(: J M. Hinds,\ r., hief 5o.2% 88 eactor Projects ection 1A Date Inspection Sunnary inspection from August 28 through October 15, 1988 (Report No /88026(DRP); 50-457/88026(DRP))

Areas Inspected: Routine, unannounced safety inspection by the resident inspectors and a region-based inspe r of licensee event report review; secondary chemistry excursion; startup test observation; operational safety verification; engineerer safety feature systems (ESF); physical security; monthly maintenance observation; monthly surveillance observation; training effectiveness; report review; contact by a merber of the public; and meetings and other activitie Results: Of the twelve areas inspected, no violations were identified in eleven. In the remaining area, one vioiation was identified regarding a failure to follow procedures durin0 the secondary chemistry excursion (paragraph 3) which had minimal innediate significance to public health a safet DR ADOCK 0500 "g6 i

_ _ _ _ _ _ _ _ _ _ _ . __ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _

-

. . -

-

l

!

DETAILS Persons Contacted

_ Commonwealth Edison Company (Ceco)

T. J. Maiman, Vice President, PWR Operations  !

K. L. Graesser, General Manager, Pov:er Operations R. E. Querio, Station Manager

• D. E. O'Brien, Station Services Superintendent t K. Kofron, Production Superintendent '

S. C. Hunsader, Nuclear Licensing Administrator [

G. R. Masters Assistant Superintendent - Operations G. E. Groth, Assistant Superintendent - Maintenance

• L. E. Davis, Assistant Superintendent - Technical Services i M. Lohman, Assistant Superintendent - Work Planning and Startup i R. J. Legner, Lead Operating Engineer '

R. J. Ungeran, Operating Engineer - Unit 1 R. Yungk, Operating Engineer - Unit 2 t B. McCue Operating Engineer - Unit 0 l R. D. Kyrouac, Quality Assurance Supervisor  ;

P. L. Barnes, Regulatory Assurance Supervisor *

R. Lemke, Technical Staff 5spervisor  ;

J. Gosnell, Quality Control Supervisor -

• R. E. Aker, Radiation / Chemistry Supervisor i F. Willaford, Security Administrator i R. tyers, Site Superintendent - Projects and Construction Services Dep L. W. Raney, Nuclear Safety  !

W. McGee Training Supervisor L

• H. E. Burgess Chemical Engineering Services Supervisor l

• R. Fay, Radiation Chemistry Foreman i

• J. Bollini, Radiation Chemistry Foreman l

• D. Kruck, Shif t Foreman  ;

S. Hedden, Master, Instrument Maintenance  ;

R. Hoffman, Master, Mechanical Maintenance  ;

J. Smith, Master, Electrical Maintenance

• C. Bedford, Regulatory Assurance [

• P. A. Lau, Regulatory Assurance I

• J. B. Cronin, Lead Chemist i

• K. Root, Chemist I

• R. Karsten Radiation Chemistry Technician l

• C. Hurschick, Radiation Chemistry Technician  !

• A. Krarean, Radiation Chemistry Technician  !

• D. Hudson, Radiation Chemistry Technician i *K. Noffte, Radiation Chemistry Technician  !

l *A. Graham, Radiation Chemistry Technician  !

l *D. Kozin, Chemist  !

l *J. Bates Chemist j

l * Denotes those attending the exit interviews conducted on October 14  !

l 1988 and at other times throughout the inspection perio ;

l

,

I 2 l t

. - - _ _

-

. .

j

'

i i

The inspectors also talked with and interviewed several other licensee i employees, including members of the technical and engineering staffs, reactor and auxiliary operators, shif t engineers and foremen, and .

elet.trical, mechanical and instrument maintenance personnel, and contract security personne . LicenseeEventReport(LER) Review (92702)

,

Through direct observations, discussions with licensee personnel, and i review of records, the following event reports were reviewed to determine l that reportability requirements were fulfilled, that innediate corrective l action was accomplished, and that corrective action to prevent recurrence had been or would be accomplished in accordance with technical f specifications

!

(Closed) 456/87047-LL: Missed Diesel Generator (DG) Surveillance Due to j Cognitive Personal Error. At 11:34 p.m. on September 28, 1987, it was n discovered that the required surveillance 1A DG was past it's critical '

date and time. The OG was declared inoperable and the surveillance was I started. This event is discussed in Inspection Report 456/88028(ORP); f 457/88028(DRP). This LER is considered close l (Closed) 456/87054-LL: Calorimetric Calculation Surveillance Performed f Outside Technical Specification (TS) Time Limit Due to Personnel Error j and Operational Restrictions. On four occasions. October 7, 21, 27, and 29, 1987, the calorimetric calculation was not complete within TS time limits. Two of the events were due to personnel errors and two were due to plant conditions initiated by a series of condensate / condensate booster pump transfers. This event is addressed in Inspection Report 456/88028(ORP);457/88028(ORP). This LER is considere<' close I I

(closed) 456/87059-LL: Missed Surveillance Due to Lost Data Shee !

On hovember 7, 1987, during the review of the September 5, 1987 Unit 1 !

"Shiftly ar:d Daily Operating Sury Allance Package," 18w05 0.1-1, 2, 3, it was discovered that Data Shee' 11. Unit 1 Mode 1, 2, 3. "TS Data Sheet l

<

Primary Plant and Accumulator 0'erability," was missing. This event is I discussed in Inspection Report 456/88028(ORP);457/88028(DRP). This LER is considered close (Closed) 456/87061-LL: Incomplete Power Operated Relief Valve (PORV) i Surveillance Due to Overly Restrictive Procedural Requirement. The cause of this event was an erroneous note in the surveillance procedure, which stated that both PORVs had to be operable to run the surveillance. This event is discussed in Inspection Report 456/88028(DRP);457/88028(DRP).

This LER is considered close (Closed) 456/88007-LL: Residual Heat Removal (RHR) Pumps Declared Inoperable Due to Irproper Surveillance Execution. On February 18, 1988, during a review of the upper rnotor bearing vibration reading observed on the 1B CS pump on February 8,1988, it was discovered that the lower motor bearing vibration readings for the RHR pumps (1B, 2A, and 2B) were

.____ ___________ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

'

. . t

-

i

not current. The pumps were declared inoperable. This event is *

discussed in Inspection Report 456/88028(ORP); 457/88028(DRP). This  :

LER is considered close '

(Closed) 457/88010-LL: Missing Surveillance Documentation Oue to  :

Personnel Error. At 8:00 a.m. on May 31, 1988, it was discovered that j documentation to verify completion of 2Dw05 8.2.1.1-1, "Unit 2 DC Bus Train Operability Weekly Surveillance," with a critical uate of May 28,  :

1988 could not be located. The surveillance was perfu.'.ed at 8:50 :

on May 31, 1988, with satisfactory results. This event is discussed in  !

Inspection Report 456/88028(DRP); 457/8S028(DRP). This LER is considered  :

close l (Closed) 456/88013-LL: Lost Composite Samples Due to Prograrmatic  ;

Deficiency. At 2:00 p.m. on June 9, 1988, the Station Chemist was -

informed that four release tank samples required for both monthly and i quarterly composite samples for TS 4.11.1 compliance were missing. The ,

cause of this event was insufficient management controls to ensure proper i disposition of composite samples once they have been analyzed for gama l activity. This event is discussed in Inspection Report 456/88028(DRP);

457/88028(ORP). This LER is considered close ,

(Closed) 456/88014-LL: Missed Surveillance Requirement for the  ;

containtrent Spray System Due to inadequate Procedure. At 1:45 ;

'

on July 2, 1988, it was determined that the 40-second sequencing timer for containment spray (CS) had not been tested in accordance with TS I requirements. The cause of the event was an error by personnel writing '

the surveillance procedure to include provisions for testing the i 40-second timer. This ev?nt is discussed in Inspection Report j 456/88028(DRP);457/88028(ORP). This LER is considered close :

(Closed) 456/88017-LL: Missed Technical Specification Corrposite Samples [

Due to failure to Implement Required Changes. At 12:00 p.m. on July 21, i 1988, it was discovered that two TS sampling requirements had not been l incorporated into the surveillance program. The samples omitted were the i condensate polisher sump discharge monthly composite and the waste water j treatment discharge quarterly composite samples. The cause of the event  ;

was a misinterpretation of the sampling requirements contained in an '

amended TS requirement by a nonlicensed chemist. This event is discussed in Inspection Report 456/88028(DRP);457/88028(DRP). This LER is considered close l (Closed) 456/88018-LL: Inoperable Valves to 1 WOO 1CB Containtrent Chiller LB as a Result of Out-Of-service (005) Procedural Deficiency. At 8:12 p.m. on March 1,1988, an Out Of-Service (005) was placed for work activities on the IB containment chiller. On April 10, 1988, an ASME surveillance for essential service water (SX) was initiated, but was partially completed due to the 005, which effected ISX1128 and ISX114 l At 11:35 a.m. on May 21, 1988, the 005 was cleared, but the surveillance j requirements for ISX1128 ard ISX114B were not performed. The cause of l the event was insufficient management controls for actions to be taken  ;

when a surveillance cannot be completed because portions of the j l

%

i

. - - .

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-

. .

'

surveillance items addressed are effected by an 00S. This event is discussed in Inspection Report 456/88028(ORP);457/88028(ORP). This LER is considered closed.

I (Closed) 457/88023-LL: Both RHR Trains Declared Inoperable Due to Procedural Deficiency. At 11:45, on September 19, 1988, during a

. discussion of the perfomance of 2Bw05 5.2.b-2, "Emergency Core Cooling System (ECCS) Venting and Valve Alignment Surveillance," performed on September 10, 1988, inadequate venting of the 2A and 2B Residual Heat Removal (RHR)trainswerediscovered. The 2A and 2B RHR trains were declared inoperable, partial surveillances were performed on the applicable groups and declared operable. The cause of the event was a deficiency of surveillance data sheets in that incomplete guidance was provided. A contributing cause of the event was failure to perform an adequate review of the surveillance procedure prior to performing the surveillance activity. Permanent procedure changes to 1/2Bw05 5.2. have been completed. A review of previously completed 1/2Bw05 5.2.b-2 was conducted to identify any other occurrences similar to this even This review revealed two additional cases. This event is discussed in Inspection Report 456/88028(DRP);457/88028(DRP). This LER is considered close The potential violations ident.fied by the above LERs are addressed in Inspection Reports 456/88028(DRP);457/88028(DRP)).

In addition to the foregoing, the inspector reviewed the licensee's DeviationReports(DVRs)generatedduringtheinspectionperiod. This was done in an effort to monitor the conditions related to plant or personnel performance, potential trends, etc. DVRs were also reviewed to ensure that they were genertted appropriately and dispositioned in a manner consistent with the applicable procedures and the QA manua No violations were identifie . Secondary Chemistry Excursion (92701)

At apprcximately 1:59 a.m. and 2:44 a.m. on September 15, 1988, shutdowns of Braidwood Units 1 and 2, respectively, were corrnenced due to abnormal secondary chemistr Based on licensee estimates, sometime between 9:00 p.m. and 9:30 p.m. on September 14, 1988, a vendor-supplied portable demineralizer system providing secondary nakeup water exhausted, and its automatic shut-off feature failed, causing thr; injection of impurities that eventually reached the secondary system of both units. The exhausted demineralizer was discovered and isolated by 10:08 p.m. on September 14, 198 At approximately 10:00 p.m. on September 14, a radwaste operator noticed a high conductivity neter reading on water coming from the portable demineralizer outlet. Opon further investigation he discovered that the local alam at the portable demineralizer was on, but the automatic shut-off valve had failed to actuate. He notified his supervisor and with his assistance isolated the portable demineralizer at approximately 10:03 ,

-

. .

!

'

!

t The inspector's review of the Station Event Recorder (SER) for the period !

!. 8:53 p.m. on September 14, 1988 through 2:04 a.m. on September 15, 1988, '

I revealed that alarms (trouble lights) began appearing in the control room l 3 at about 9:43 p.m., indicating problems on the secondary sampling panel, l l and at about 10:32 p.m., indicating steam generator sampling blowdown i

! panel problems. Radiation Chemistry personnel were unaware of the !

j exhausted demineralizer and the control room trouble light l

.

1 At approximately 11:00 p.m. on September 14, 1988, a RadiaH on Chemistry [

l Technician (RCT) discovered abnormal cation conductivity, sodium, and pH l i readings on the steam generator sampling panel and notified the Radiation l l Chemistry Foreman (his supervisor). The Radiation Chemistry Foreman then checked the secondary sampling panel and also found abnormal reading !

'

He notified the shift control room engineer (SCRE) by 11:30 p.m. and reported chemistry values above Action Level 3 due to an unknown cause.

l

<

No mention was made by the SCRE of the exhausted demineralizer at this t

I tim !

t

,

! At approximately 12:30 a.m., the Radiation Chemistry Foreman notified l the Lead Chemist by telephone of the event. The Lead Chemist, still ;

,

unaware of the exhausted demineralizer and acting on previous experience, i i requested that the condensate polishers (cps) be taken off itne. The l I Lead Chemist and a Station CPemist arrived at the plant at 1:30 ;

and by about 1:45 a.m. informed the control room that Action Level 3 chemistry values had been confimed. At about the same time, Radiation ;

l Chemistry personnel learned of the exhausted demineralizer problem from ;

1 _

the Shift Foreman, who by this time had correctly deduced that this had ;

] caused the chemistry problem in the secondary syste l

l Once the source of the secondary system contamination was known, a !

{

'

plan was developed and implemented to clean up the system. Secondary chemistry parameters were returned to normal, and by September 21, 1988,

! both units were restarted.

i A Region !!! inspector was on site on September 16 and September 25-27,

{

1988, te evaluate the event. The irspector determined that the event i

was a result of lack of mana3erent control of vendor services. The .

vendor was allowed to set up a d operate the demineralizer system without !

! oversight on the part of the licensee. No procedures were in place to {

j confirm the adequacy of the installation and its operation. This failure ;

was exacerbated by the lack of comunication between the control room and !

! Radiation Chemistr . Radiation Chemistry personnel were not initially j notified of the ex austed demineralizer problem and subsequently were not .

notified of secondary system probicas being indicated by trouble lights l l in the control room. Because Braidwood Alam Response Procedure BwAR !

j 1-1-b7, "Secondary Sampling Panel / Sink Trouble," Revision 52, April 1987 J

requires irmediate nntification of the Radiation Chemistry Department of 1 J secondary sampling panel alams, failure to nake this notification is a I

<

violation of Technical Specification 6.8.1.a. (50-456/88026-01(DRSS);

50-457/88026-01(DRSS))

!  !

! 6 I

! I E  !

--

,

,

e .

i

.

,  !

i It is likely that knowledge of the precursor problem with the deminera- i lizer would have considerably hastenti the diagnosis of chemistry :

problems when they occu* red in the secondary system and should have l allowed the decision to begin plant shutdown to be made earlier. The r licensee needs to review the matter of timely confirmation of chemistry l conditions and iraplementatinn of Action Level requirement t

The effects on the steam generators and on the condensate storage tanks ;

of operating at full power with secor.dary chemistry parameters above '

Action Level 3 for several hours also need to be reviewed, and the licensee has agreed to provide the NRC with a report of its evaluation of ;

these effsts (open itera 50-456/88026-02(DRSS);50-457/88026-02(DRSS)). ,

!

One violation and one open item were identified, i Startup Test Observation (72302) j The inspectors witnessed performance of portions of the following Unit 2 l startup test procedures in ordt.r to verify that testing was conducted in j accordance with the operating license and procedural requirements, that j test data were properly recor6ed, and that performar,ce of licensee l personnel cond'cting the tests demonstrated an understanding of assigned duties and responsibilities:  ;

i NR-79 Plant Trip from 100% Power 1 l

TG-90 Nuclear Station Supply System Acceptance Test

' Operational Safety Verification (71707)

The inspectors conducted routine plant tours during the inspection period to make an independent assessment of equipment conditions, plant conditions, security, fire protection, general personnel safety, ,

! housekeeping, and adherence to applicable regulatory requirements, n

'

During the tours, the inspectors reviewed various logs and daily order l interviewed personnel, and attended shif t briefings and plan of the day !

meetings. During the shift changes, the inspectors observed operator, shif t control room engineer, and shift engineer turnovers and panel walkdown These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications,10 CFR, and administrative procedure No violations or deviations were identifie . Radiological Protection (71709)

The inspectors selected portions of the licensee's radiological program to verify conformance with facility policies, procedures, and regulatory requirements. Observed aspects inclucN the health physics managers'

awareness of any unusual conditions or callenges, the implementation of

.___ ___ __ ____ - _____ _ ____________________ _______ __

-

. .

{

,

, the ALARA program, the use of Radiological Work Permits (RWPs), the control and monitoring of radiation exposures, including work in high radiation areas if applicable, and the control of radioactive material.

l

. No violations or deviations were identifie ' Engineered Safety Feature (ESF) Systems (71710)

l During the inspection, the inspectors selected accessibis portior* of ,

several ESF systems tc verify their status. ConsideratiJn Was given to ;

<

the plant mode, applicable Technical Specifications Limiting Conditions i for Operation Action Requirements (LC0ARs), and other applicable l i requirement '

i Various observations, where applicable, were made of hangers and I supports; housekeeping; whether freeze protection, if required, was :

installed and operational; valve positions and conditions; potential *

ignition sources; major component labeling, lubrication, cooling, etc.; i

'

interior conditions of electrical breakers and control panels; whether !

instrumentation was properly installed and functioning and significant -

process parameter values were consistent with expected values; whether ;

instrumentation war calibrated; whether necessary support systems were operational; and whether locally and remotely indicated breaker and t valve positions agree During the inspection, accessible portions of the following ESF systems / components were walked down: '

Unit 1 )

t 1A Diesel Generator  ;

IB Ofeeel Generator i 1A Safety Injection System  !

1B Safety injection System I Unit 2  !

I 2A Diesel Generator  !

2B Diesel Generator I 2A Safety injection Systen  !

2B Safety Injection System No violations cr deviations were identifie . Physical Security (71881)  !

At various tires throughout the inspection period, the inspectors monitored compliance with the Physical Security Plan (PSP). Selected (

observations were made of ma wing levels and collateral duties of l assigned personnel; access control equipment and processes, such as !

x-ray machines, netal detectors, explosive detectors, and other search I

!

l

l

-

. _ _ _ _ _ _ _ J

.

i

.

i

!

'

t

,

mechanisms; whether protected area (PA) and vital area (VA) barriers were  !

properly maintained; whether procedures were properly followed; whether compensatory measures were appropriately used when required; whether persons in the PA and VA were properly badged and escorted if required;  ;

whether variour detection / assessment aids, such as fences and r illumination of the PA, were operable; and whether TV monitors had i sufficient clarity and resolutio "

i Marijuana Found Growing Wild in Owner Protected Area  !

On September 22, 1988, the re;,ident inspector was notified by the Station ,

Security Supervisor that some plants suspected to be marijuana were found i growing in the owner protected area by the cooling pond spillway, l.ocal '

police narcotics agents were notified, and they identified approximately i 200 plants as uncultivated marijuana. The licensee then destroyed the l plants. The narcotics agents said that it was not unusual to find '

marijuana growing wild. The resident inspector reviewed photographs to I verify the destruction of the plant '

No violations or deviations were identified, l i

! Monthly Maintenance Observation (62703) j Station maintenance activities affecting the safety-related systems and f components listed below were observed / reviewed to ascertain that they i were conducted in accordance with approved procedures, regulatory guides l and industry codes or standards, and in confortN.nce with Technical j Specifications, j

The following items were considered during this review: the limiting  !

conditions for operation were met while components or systems were  !

removed from and restored to service; approvals were obtained prior to initiating the work; activities were accomplished using approved  ;

procedures and were inspected as applicable; functional testing and/or i calibrations were perforred prior to returning components or systems to l service; quality control records were maintained; activities were l accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemented. Work requests were reviewed to detemine the status of outstanding jobs and to assure that priority is '

assigned to saftty-related emipment maintenance which may affect system perfomanc Maintenance activities m o- 'Inwing equipment were observed and  !

reviewed:

Unit 1 IB Solid State Protection System Train return fuse and holder ,

replacement, i Unit 2

i t

. , _ . _ , - _ . - . _ , _ _ . _ _ . _ - - , _ - -

.

. .

t

.  !

i i

Main Condenser Tube removal and pluggin MainSteamIsolationYalve(MSIV) failed 0-Ringandfour-way [

valve repai ,

,

r 2C Main Steam Isolation Yalve four-way valvs rebuild, test, and ;

replacemen i t

The inspectors monitored the licensee's work in progress and verified ;

that it was being performed in accorda9co with proper procedures and :

approved work packages, that 10 CFR SU.59 and other applicable drawing l updates were made and/or planned, and that operator training was ;

conductad in a reasonable period of tim i

No violations or deviations were identifia i 10. Monthly Surveillance Observation (61726)

The inspectors observed surveillance testing required by Technical r Specifications during the inspection ,-eriod and verified that testing !

was perfonned in accordance with adequate procedures, that test i instrumentation was calibrated, that limiting conditions for operation '

were met, that removal and restoration of the af fected components were ;

accomplished, that results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than thi '

individual directing tii test, and that any deficiencies identifiet [

during the testing were properly reviewed and resolved by appropriate !

management personne ;

The inspectors also witnessed portions of the following test activities: j Unit 1 I

!

18wVS 7.2.1.a-1 Motor Driven Aur.iliary Feedwater Furp Monthly Surveillance Unit 2 l

[

2BwYS 7.2.1.a-1 Motor Driven A utliary Feedwater Purp Monthly l 5, veillance j 2Bw!S 3.1.1-233 Modes 1 through 6 Analog channel Operational I'

test of Nucleu Instrument System Power Range h41 N42, N43, N l 2SwVS 3.2.2-1 Engineered Safety featurcs Response Time Surveillance  :

L 2B4 5 8.1.1.2.a-1 2A Diesel Generator Operability Monthly I (Staggered). Semi-Annual (Staggered), and !

18-month Surveillances 10 l l

>

. .

.

No violations or deviations were identifie . Training Effectiveness (41400, 41701)

The effectiveness of training progiams for licensed and nonlicensed personnel was reviewed by the inspectors during the witnessing of the licensee's performance of routine surveillance, maintenance, and operational activities and during the review of the licensee's responte to events which occurred during the inspection period. Personnel appeared to be knowledgeable of the tasks being performed, and nothing was observed which indicated any ineffectiveness of trainin No violations or deviations were identifie . Repo*t Review

, During the inspection period, the inspector reviewed the licensee's Monthly Performance Reports for August and September 1988. The inspector confirmed that the information provided met the requirements of Technical Specification 6.9.1.8 and Regulatory Guide 1.1 The inspector also reviewed the licensee's Monthly Plant Status Report for August 1988 and the minutes of the Braidwood Corporate Overview Meeting held on September 28, 198 No violations or deviations were identifie . Contact by a Member of the Public (94703)

On September 2,1988, the senior resident inspector (SRI) was contacted telephonically by Mrs. Rose Favero, who lives in the immediate vicinity of the 8raidwood station. Mrs. Favero stated that during the evenings and occasiordly during the day, she could hear the noise of operating equipment and the plant puolic addetss (PA) system at her home, She stated that she had complained in the past to Comonwealth Edison's Corporate Public Relations group and had gotten some satisfactio l However, recently she had heard more disturbing nonprofessional use of the FA system and was concernea about the safety of the plant if this was an example of how the plant was being operated. The SRI assured -

Mrs. Favero that the plant was being operated safely and that the NRC and CECO were aware of the PA system abuse and were trying to locate the individual (s) involved. In addition, the SRI infomed her that the steam generator relief valves lift on occasion during reactor trips and that I she should not be concerned about i He also reminded her that if a,1 actual event were to include the public, the prompt public notification system (sirens) would be used to alert the public. He also reminded her about the publication that was mailed to her and what action to tak She stated that she could not recall the pamphlet, but would pursue her concerns with the licensee's Public Relations grou The SRI discussed this matter with station management and suggested reducing the volume of the PA speakers that could be heard at the property t:oundary. This was acknowledged and such an atten#pt was being mad .-_

a . .  !

.

The SRI relayed this to the Region III Public Affairs Offic . Meetings and Other Activities (30702)

Monthly Plant Status Meeting Meetings were held on August 30 and September 30, 1988, between the Region III Director of the Division of Reactor Projects (DRP), The Vice President - PWR Operations, the Station Manager, and members of each of their staffs. The purpose of the mee' ' 'as to discuss the status of Braidwood with respect to present % .y issues and items specific to Braidwood. During the August 30 meeting, the subjer.ts discussed were current plant status, plant schedule milestones, a performance sumary on Licensee Event Reports and Deviation Reports, recesit reactor trips, security, NRC Infonnation Notice 88-46 and Supplement I regarding defective refurbished circuit breakers, the cooling lake status related to potential silting ani pumping makeup water, Bunker Pamo containment penetrations, and a surveillance LER review. In addition, the NRC contingent had a discussion with the Station Outage Coordinator and a tour of the control room, where the Director, DRP discussed current issues with a number af licensed reactor operator During the meeting on September 30, the items discussed were current status, milestone / schedule review, an updated performance summary including recent reactor trips, general and specific surveillance program issues, and the chemistry excursion. ~

No violations or deviations were identifie . ExitInterview(30703],

The inspectors met with trie licensee representatives denoted in paragraph I during the inspection period and at the conclusion of the inspection on October 14, 1988. The inspectors sumariud the scope and results of the inspection and discussed the likely content of this inspection report. The licensee acknowledged the information and did not indicate that any of the information disclosed during the ir.spection could be considered proprie'.ary in natur i

. .

. .- .

,

REPORT / LETTER TRAVELER RIII REPORT / LETTER TRAVELLER TOTAL DAYS TO ISSUE

___.__ __ __ ________ ___ __ ____ _____ _____ __________ _____ ___ _____ _

Licensee  : Draft Completion Date: Report No(s):  :

150-456/88G/f(DRP);

__ COMMONWEALTH EDISON  : Initial Typing:  : SO-4 S6_L88.f_Q61DRP )

Facility (s): __

Inspection End Dates

: Received Start End :

BRAIDWOOD 3 3 Inspector Reviews  : OC.To BER ff', pg gg :,

s UNITS i &2  : Start End, Inspector (s):  :

: Date Mailed:  : TONGUE  :

License No(s):  :  : TAYLOR  :

NPF-72; * Date Trans. (FC) /c .10-8E : G . V AA) O sckt s

NPF-77  : Date Received ___  :

_

i  :

REVIEW PROCESS  :

Data

Doc  : Insp/PM : : : : : Mgmt. Unit  :

j_ Format __ _ __ I n _ _Out: In : Out: In n (:s t : In : Out: In : Ou_t : In Out

: : : 3,p  : : : : : :  :  :

: : : : *7 : : : : : : :  :  :

: : : : : : : : : : :  :  :

: : : : _: : : :_ : :  :  :

: : : : : : : : : : :  :  :

.

: : : : : : : :  :  :

: : : : : : : : : : :  :

2  : : : : : : : : : J :  :  :

: : : : : : : : : : :  :  :

: : : : : : : : : : :  :  :

: : : : : : : : : :  :  :

.: : _: : : : : : : : , _ _ _

_ _ _

:Iceue Dates

_

807271563_ OCT27jg ,

Note  : Licensee HQ(DMB)  :

:

f

No___LCOMMENT

:  : Proprietary Review Nati :

3, _ _

_ _ _ _ _ _ _ _ . Telephone _ __

:  : DUE RECEIVED :

: Written _ _ _ _ , . . _ .

1 _. ,__

: __ _ PUE FEQRVED _

_ 1__  : Responue  :

. _ _ . _ . - _ _ _ . _ _ . _ _ _ . _ . _ _ _ _ _ _ _ .

1ftns __ _ LOUE ISSUED RECEIVED  :

: Thank You Letters

:  :  :

:_ _ _ _ _ _ DUE_ ISSUED .:

.- 2 --

- _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _____ ._. _ _ _ _ _ _ _ _ __ ____ _ ___ ___ _ __ ___ ______

. . .

NRC FORM 766 U.S. NUCLEAR REGULATORY COMMISSION  : PRINCIPAL INSPECTOR (6-83)  : TONGUE IE MC 053S INSPECTOR'S REPORT  :

OFFICE OF INSPECTION AND ENFORCEMENT REVIEWE -

INSFECTORS: T. TAYLOR g4g f g

SITE NAME  : TRANSACTION: DOCKET NO REPORT (15-19):NEXT INSPE : _ TYPE (1)  : (2-14) 8-pIGITS: N : SE : M : Y BRAIDWOOD  : XI-INSERT  : 05000456 :880 0/, A  :  :

M-MODIFY  : 05000457 :88046: B  :  :

__D-DELETE :  : : C  :  :

__R-REPLACE :  : : D  :  :

~

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ?*******************************************

PERIOD OF INSPECTION  : INSPECTION PERFORMED BY (33)

FROM

(21-26)  : TO :(27-32) __1-REGIONAL OFFICE STAFF : OTHER:

gg  : YR : MO : DAY :

YG _X2-RESIDENT INSPECTONc

DQY

-  : : __,3-PAT  :

0f : ./8 1 98 : /0 /f 88 _

QRGANIZATION_ CODE OF REGION /HO CONDUCTING ACTIVITY: REGIONAL ACTION (37)

BEGION (34) : DIVISION (35)  : BRANCH (36)  : 1-NRC FORM 591 3 a 2  : 1  : X 2- REGIONAL OFFICE

: LETTER

TYPE OF ACTIVITY CONDUCTED (38-39)

X_02-SAFETY __06-MGMT. VISIT __10-PLANT SE __14-INQUIRY

__03-INCIDENT 07-SPECIAL 11-INVENT.VE __15-INVESTI-

__04-ENFORCEMENT __O8-VENDOR __12-SHIPMENT / EXPORT GATION 05-MGMT. AUDIT 09-MAT _. ACCT 13-IMPORT

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • t3**************************************

:  :

, INSPECTION / INVESTIGATION  : TOTAL NC OF  : ENFORCEMENT REPORT C.ONTAIN FINDINGS (40) _ VIOLATIONS &  : CONFERENCE :2.790 INFO.

<

&_1_ B _JQ : D :  : DEVIATIONS  : HELD  :

__J

: 1-CLEAR  : (41-42)  : 2-YES (40)  : (44)

X X

: 2-VIOLATION __ . _ _ _

:  : _: 3-DEVIATION .JL B Q_ _D_: _A.: ? : _C . : D__4 A : D .: G_ D ._

:  : : 4-VIOLA 1 ION &  : :  :  : :  :  : : 't :

,__;  : _: : DEVIATIOfj,_,:,[:: E-* : ,, s _ _ _ :  :  :  : _: : :

, i LETTER OR REPORT TRANSMITTAL _DATE_

- _

NRC FORM 591  : REPORT SENT

OR RE : TO HQ. FOR  :

'

s LETTER ISSUED : ACTION  :

(45-50) _: (31-56)  :  !

MO DAY : YR : MO : DAY : YR  :

,_ R L .,. E L __3..Y X _ ,. J F L., M - _ :  :  : :  :  :

'

i

- 3- ,

i

,___ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ , _ _ _ _ _ _ _ . . _ _ __

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. .

NRC FORM 766 MODULE INFORMATION REC- : MODULE NUMBER INSP :  : : : S :  : : MODULE REO FOLLOW-ORD :  : : : : I T : P  : : UP  :

:- P : : : : NA : EC  :-a : : P  : :

: : : R : : : P : SF :RO  : : : : R  : :

-: : C : O : : : R : PF : CMT :  : : C : O  : :

N,: : M H : C N : : : I : DE  : EPO : S:  : M H : C N  : :

U : P : A A : E U' L : : O : I CH : NL  : T: P: A A : E U L :-

T : M :. H : N P : D M E : * : R : RTO : TED : A: H: N P : D M :E :

Y : B : .A : U T : U B :V : S ': I : E I U : ATA : T: At U T : U B :V :

P : E : S : A- E : R E :E : E : T : COR : r dT : U S: A E : R E :E :

E : R : E : L R : E R :L : O __: Y : TNS : E. D__ E : S: Es L R : .E R  : L._ :

.

_1 :2 3: 4 : S 10: : 12:13 15:16 18:19:20:21 26:

: : : : : : :  :  : : : :  : :

B _ _ :@ /_: 6~s M O 3 ,L ,t o 3 :

~

A : : C r o: I _ _ _2 0 t  : : : _ _ _ _

'

: :  :  : : : :  : :

B _o: g _e _i _: _ i _c_ i _ i _  : _i _i _i _:

: : :  : :  :  :  !  : :

._n_ ai.h _fs,3: / i_Z:.d: 6:_:: - A  : cio: 2:: oi8:o:Q.:_

. . _ _:_: : __

-

'

: :  : : : :  :

B .: : O,s t, d_: 0 :%: O: L _ _:

_

_: _ _ : ,__  :

:  : : :  :  : : : :  : :

4 B son 3: .5~:I 4:: 7__,: ,0 _3: _: A :  : _c_, : f: _f, ,0_, 3: O__ g,_, _,_ _ :  : _ _ , ,:, , _ _ : :

: :  :  : : : :  : :

B : 3,g}: 23,5L b : b 0 3 4_: __,, _:  : _ ___ : :

: : : : : : :  :  : : : :  : :

B : O:_ Y f a _7: /: _Z:,Q :,7 _ : A : 3,Q 5i.lz O: B: 0 a.C_:,,_: _ :  : _: _ _:_ : :

: :  :  : : : .:  : :

B : : _Q Ji' .2 : _Q,:B:0 : C: _ , _: __:

_

,__ _

_ , _ _

,

a : : : : : : :  :  : : : :  : :

B :0:s: .<s 7: / : 7: O:2 _: A : 3 ,C_ : 0. 6 0 s'{ O_:C,_ : _: _ :

:

____: : : :

:

: :  :  :

B :O:O( ,M., th a b s,__ __, 3  :

__, 3 ,,,,_ : _ , , , , , ,:

: : : : : : : J  : : :  : :

B sh:_ I: , h: ,, _/_,: 1: [ @ ,,,,,,, - A :  : M: [ f Q.,: 026: 6: 1 :__._i _ :  : :

_ , _ , ,_, t _ : ,__,:  ;

'

: :  :  : : : :  : "

-

-_ I ..E_. I _._. M [a rI b : . C< _. : _ _. ._ I I _ : : _

i a : : : : : :  :  : : : :  :

,,_E.,_ : @_ 2: _,,,[: d s _,/__t _ ,[ 2 ,,_,, A : ,,,C): ,C: b : [ b k: ,,,,,,s _,_,

: ,,,,,_ ! ,,,,1 ,_,, a

:  :  : : : :  : :

. 313, _: ,Q,3 _S ,, s k: :b:b:_i_: _ _: _ : ,_, : _ _:

'

Jh : : : : :  :  : : : : f bsQ Y: _7. _I : _O. *M _,3 - A - :M M D:__  : :_ : : ada  : : :

: :  :  : : : :  : :

., B : : O:Q k s d a k ,b.,, b a __,1 : ,, ,_,, ,,,,,,3 ,,,,_, J ,,, ,,_,

: : : : : : :  :  : : : :  :

B __ : hs h,

_: : 0 :[ _, ,, 13 ,.,_ , i r : / : _h ,__ _, i __. : ,_ ,,, s _,,,, : , , , , , _: 4,,,, ,,,,_,,,s,,

: :  :  : : : :  : :

i l [1,[ M  : : : : : 1 ,, _ : ___ : ,_ _,,,, i

• *  : : : : :  :  : : : :  : :

_ [j d * N : j a,Q k i A : 4--O*1Or [-"1_, : _ _ _, J  : : : ___,,_,,,,,3,__t

• CIRCLE SEQUENCE IF  : : :  :  : : : :  : :

VJ.0LATION OR DEVIATION  : H : MT@rY1  : : : : : _ _ i ___ t _ _:

4 -

.

NRC FORM 766 MODULE INFORMATION REC- : MODULE NUMBER INSP :  : : : S :  : : MODULE REO FOLLOW-:

ORD :  : : : : I T : P  : : UP  :

: : : P : : : : NA : EC  : : : : P  : :

: : : R : : ; P : SF : RO  : : : : R  : :

: : C : O : : : R : PF : CMT 1  : : C : O  : :

N :  : M H : C N : : : I : DE  : EPO : S:  : M H : C N : :

U : P : A A : E U :L : : O : I CH : NL  : T: P: A A : E U :L :

T : M : H : N P : D M :E : * : R : RTO : TED : A H: N P : D M :E :

Y: D : A : U T : U D :V : S : I : E I U : AT A : T A: U T : U D :V :

P : E : S : A E t R E :E : E : T : C0R : GET : U: S: A E : R E :E :

_E : R : E : L R : _E _R L : O _ _: Y : _T N S : E__D E : S: E L R : E R :L :

1_:2 3: _4 : 0 10: _ LE:_13 1_5:16 18:19:20:21 26:

: : : : : : :  :  : : : :  : :

_D1/_[ 3_r_: _: _b : 1: ,d_1 h _

_

0:j:  : : : : : : 3

_: : 1 1

: :  :  : : : :  : :

D : : O : / r h : ,_, _ : _ : ,,,,,,,,, : ,,,,_, : __,,,  : : : : :

:  : : : : :  :  : : : :  : :

B : f_ : y: ___ $ 3 3: _Q:) _: A :  : _Q :0: ,,f_ : ,,,._ : _ : ,,_ : ,_, ,,,, , _,_ :  : __, __, 8 _ : _1

:  :  : : : :  ! :

B : ,d C f_:  : : : : __,1 : __ t ,_ : _ , s __

: : : : : : :  :  : : : :  : :

B : : :  : 3  :

,a__,,,,,,,,,___ A : : 3 : : 1 : _ ,,,,,,,8 : : __, 3 ,,,,,, 8 ,,,, 3 ,,_, 3

: :  :  : : : :  : :

.,

i B : : __,: _1,_,,,, _ t ,, ! __,, a _,,, :  : : _,,, 8 ,,. . : _ _,_

: : : : : : :  :  : : : : *

D 1_: _ :_ ,, _._: : : : : : A 3 : _,_: _, _ __ : t _ : __ _: _: _,1  : __ : ,,_t_: _,_

: :  :  : : : :  : :

_[1_ t : : : : 1 8 : : : : : : : :

: : : : : : :  :  : : : : *

D : : : 1 : : : : : 3 A : : : : : : : : : : : _ _ 1 _ ,s _ __

: :  :  : : : :  : .

B : : : : : : : : 3 : : 2 , _,1, _ : _, _ t

: : : : : : :  :  : : : :  : *

D : : :  : : : : : : : A : : : : : : : : : : : 8 : : :

: :  :  : : : :  : :

D : 1 : 1 : : : : 1 : : : : :

: : : : : : :  :  : : : :  : :

,,,E,j. , , t , s , , I : : : 8 : 1 A : : : _ J ,,,, , ! ,,,,,,,_ : ,,,,s__.__,,,,_,,,s,_,.,,_,,,,,,,,,,,,,,,t,_,!,,,, ,__, i

: , a  : : : :  : *

I fi . I _ ; . . : _ : ,,,_, ,,,,,, a _ : ___ _,,,: _: ,_,, a t : 8

t & : : : 4 :  :  : : ! :  : 8 E _. I _. I _ 1. _ ._ . : ,,,,_ ! : : : A : : 1 : _,_____,,,_,,s,,,,,,,,,,,__',t,,,,,t_l_,,,t s 1  :  : : : :  :

__

t _D_ ; __ ,: ,_,1  : : : : : : 1.,,_ ,._,1,_i _ :

8 : : : 1 I : I  : i :  : :

_Q_ _ _:  : : : 3 : : : A .: : 1 I : 1 I : I : __I__t_i__

: :  :  : : : :  : :

,,__D ., _ : _ , 8 ,, 3 ,,,__ : _: , , , , _: _:,__: __,,: I : : : :

3 3 : : : : :  :  : : : :  : :

D : : _ _ _ __ .: : 1 : : A : : : : : : : : : : : 1__!__ _ __

• CTRCLE SEQUENCE IF  : : 1  : : : :  :

VIOLATION OR DEVIATION  : D : : : : : : : : : : : __ __ _ __

_ 4 _

. _

F

, .

NRC FORM 766 INSPECTOR'S REFORT (CONTINUATION)

REPORT : MODULE NUMBER :  :

DOCl:ET Nt tMBER  : NO : SED: : : : : : : :  :

30 S :0 :0 30 :4 :D :6 : 880 A b  : o/: VIOLATION SEVERITY  : SITE :SUPL:

: : : : : : : : : : OR DEVIATION :RELATED: :

30 :D =0 20 20 :4 :S :7 : 880 46 30/: 1 : 2 : 3 : 4 : 5 : D A: : "I__:

: : : : : : : : : , : : : : : :B: : r :

: : : : : : : : : : : _ _ _: : )C :: : : : :

: : : : : : : : : :  : : :

: : : : : : : : : :  : : :

__: : :

__ __ __ __ __ __ __

: : : : : (27)  : (28) :(29):

VIOLATION OR DEVIATION (ENTER UP TO 2400 CHARACTERS FOR EACH ITEM)

$% +b Y') V

4

6

8

10

12

14

16

10

20

22

24

26

20

30

32

34

. , _

_

.

. .

SALP FUNCTIONAL AREA ASSESSMENT AND PRELIMINARY INSPECTOR EVALUATION FORM Eacility: BRAIDWOOD _ Inspection Rrgtori No.: 456/880 : 457/880

FUNCTIOrfAL AREAS

_  : x : I :II :III:IV : V :Dev: Unit:3atina

PLANT OPERATIONS  : : : : : : : : : :~

: : : : : : __: : : LO ;

RADIOLOGICAL CONTROLS  : : : : : : : : : : : #

z  : : : : : I : : : : /. I :0:

MAINTENANCE  : : : : : : : : : :Pt

: : : : : : : : SO :E:

SURVEILLANCE  : : : : : : : : : R:

: : : : : } : : : 4. 6, :A:

s FIRE PROTECTION  : : : : : : : : : :T:

: : : : : : : : : :I:

EMERGENCY PREPAREDNESS  : : : : : : : : : 0:

: : : : : : : : : O- IN:

SECURITY  : : : : : : : : : :S

: : : : : : _,

a : 2 : :

OUTAGES  : : : : : : : : : : ~:

: : : : : : : : :_ 1 :

QUALITY PROGRANS & ADMI * * : : : : : : : :

CONTROLS AF,*ECTING OUALITY : : : : : : : : A :

LICENSING ACTIVITIES * : : : : : : : : :

: : : : : : : : : 2 :

• TRAINING & OUALIFICATION * : : : : : : : : :

_ EFFECTIVENESS  : : : : : : : : : :

1 ENGINEERING & TECHNICAL SUPPORT : : : : : : : : : :

: : : : : : -

: A :

: : : : : : : : : :

a a : : : : : : : : :

: : : : : : : : : :

_: : : : : : : : _

: : ! : : : : : :

: : : : : : : : : :

: : : : 4 : : : : :

_

;__:_ : : : : : :

: : : : : : : : : :

_ _ . ,1 : : : _: _1 : : :

: : : : : : : :

1  : : : : : : : : : :

• Functional areas for Construction and Oper.Ttions CRI TER EF OR 2hlfR[1MLNft_ CATEGORY RATING Mr.n ag emen t Involvement in Assuring Gualit . approach to Resolution of Tec hn ic a ' Issues from a Safety Standpdin . Responsiveness to NRC Initiative . Enforcement Histor . Operational and Construction Event . Staffing (including management).

'.ATING KEY: (For Categories 2 - Declining and provide narrative basis for conc 1usion)

Category 1 Category 2 - Declining Category 2 Category 3

[ Inupector(n) concerns adequately addressed or

_

Inspection Evaluation form being proconse . _ ,

LNd I n r p e c. t o r T, TONGUE jojkodf Section 'f-Ch' [ M ignatuYEI (Date

'# /fS (Signature) (Dat6)

C6 k,r

- 6 -

1