IR 05000254/1978010

Insp Repts 50-254/78-10 & 50-265/78-20 on 780713-0803.No Noncompliance Noted.Major Areas Inspected:Plant Operation & out-of-svc Activities

ML20062B751
Person / Time
Site:	Quad Cities
Issue date:	09/18/1978
From:	Jackiw I, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20062B749	List: IR 05000254/1978010 IR 05000254/1978019
References
50-254-78-10, 50-265-78-20, NUDOCS 7811010076
Download: ML20062B751 (6)

Text

.

'

,~ ' -

.

U.S. NUCI. EAR REGL*LATORY CO.'OiISSION '

0FFICE OF INSPECTION AND ENFORCEMENT

,-

a

_ REGION III

.'

Report No. 50-254/78-19; 50-265/78-20 Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 i

Facility Name: Quad-Cities Nuclear Power Station, Units 1 and 2

Inspection At

, Quad-Cities Site, Cordova, IL

! Inspection Conducted: July 13-14, 19-20, 26-27, August 2-3 and 10-11, 1978 l "

/ i i

$ s,f ' ' ;4 C l * ^~ p ,*!_/- -/ j Inspector: N., Jackiw b C w ijg Approved 3y: R. C. Knop, Chie Reactor Projects Section 1 Insoection Summary Insaection on Julv 13-14 19-20, 26-27 and August 2-3, 10-11, 1978 (Recorts No. 50-254/78-19 and No. 50-265/78-20)

Areas Insocceed: Review of plant operations and out-of-service activities; reviev ei safety limits, li=iting safety system settings and limiting con-dicions for operations; review of procure =ent activities; review of rad-l waste barrelling activities; 10 CFR Part 21 review; and licensee event

'

report followup. The inspection involved 74 inspector-hours onsite by one NRC inspecto Results: No items of ncncompliance or deviations were identifie ,

,

i

-]S//GK G 75  ;

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

.

.*

DETAILS

.

. Persons Centacted

.

• N. Kalivianakis, Station Superintendent K. Graesser, Ad=inistrative Assistant J. Gudac, Assistant Superintendent

• L. Gerner, Technical Staff Supervisor R. Bax, Operating Engineer. Unic 2 G. Conschack, Operating Engineer. Unit 1 T. Tamlyn, Lead Cperating Engineer

'*D. Thayer, Quality Assurance Engineer, Maintenance R. Demig, Assistant Storekeeper The inspector _also interviewed several other licensee employees including shift engineers and foremen, reactor operators, rad-waste operiting personnel, technical staff personnel, storeroom personnel and quality control personne * Denotes :hese present at the ext: intervie . Licensee Action on Previous Inscection Findings (Closed) Unresolved Item-(254/77-26): Inoperable Control Rod Accumulators. The inspector confirmed that the licensee has been in contact with NRR and has agreed to comply with the intent of Technical Specification 3.3.D and 3.3.G which states that no two control rods can be inoperable in any nine-rod array configuratie . Procurenent Procurement activities were reviewed to ascertain whether the purchase of ccmponents, =aterials and supplies used for safety related functions, is in confor=ance with the licensee's approved quality assurance program and implemen:ing procedures. The inspector verified that procure =en: specifications used in the purchase of :sterial included proper approval; quali:y control inspection require:en:s; quality record requirements; and evidence of material conformance to procurecent requiremen:s. The folicw-ing c:sponents were inspected: Standby Gas Treat:ent System isola:1:n valve; 250V 3a:tery Charger par:s; and three valve

=anifold for s:a:1on surveillance.

i i The inspect:r also confir:ed : hat spare par:s used in safe:y related func: ions were supplied by an approved vender; vere

,

e e i

_ . . _ _

- . . . . - - - .. .- _ . . -. .~.

5 '

' '

.~

.

v .

.

, inspected upon delivery; and are being handled in accordance I

with measures established for control and separation of. con-

,

forming and nonconforming materials, parts and components. -

' *

No iteta of noncompliance or deviations were identified.

4 Solid Radwaste

,

Process' wastes, such as filter sludges and spent resins are

,

collected in hoppers, dewatered, loaded into 55-gallon dru=s

-

and mixed with a solidifying material. After-loading.

the

'

drums are moved to a capping station where drum lids are attached and secured. The capping area is separated from the operator

,

area by a concrete wall penetrated by an opening through which

, the band and lid holder is moved into the capping are The inspector observed the solid radwaste barrelling operation-and noted that the drum filling and capping operations are performed with remote equipment and conveyors. .

No items of noncompliance or deviations were identified.

,

5.- Limiting Safety System Settings and Limiting conditions'for Operations.

!. This area was reviewed to' ascertain whether reactor operations i are in conformance with Technical Specification requirements

for safety limits, limiting safety system settings-and limiting

conditions for operations.

< The review included observation.of process instrumentation monitoring current operations; observation of panels and annunci-ator boards for equipment "out of ~ service;" review of monitoring

instrumentation charts; and review of other' records such as main-1 tanance, scram and deviation record No items of noncompliance or deviations were identified.

f Out of Service Task Force Conclusions i Equipment outage control events that occurred 'at Dresden have been reviewed and evaluated by station managenent. The follow-ing actions have been taken relative to the Investigating

Cc==ittee's reco=mendatiens: Emphasis for rigorous co=pliance with the out-cf-service procedures.

l-3-

!

i ,

,

r

.

-

.

. Procedures dealing with shif t change, cperating logs and equipment centrol and tagging have been added to the

-

required reading list for all operating license holder Assignments of Technical Staff Engineers have been made to work with station Operating Engineers on specific projects during normal plant operation and for short outage No items of noncompliance or deviations were identifie . 10 CFR Part 21 Inspection This area was inspected to ascertain whether the licensee and individuals subject to Part 21 regulations have established and are implementing procedures and controls to assure the reporting of defects ,and nonce =plianc The inspector verified that the following controls have been established for i=plementation of Part 21 requirements: Quality Procedures 15-51,15-52 and 15-53 have been revised to include evaluation of deviations with regard to Part 21 requirements and informing the Commission when receiving information of a defect or reportable ' failure to compl Maintenance of Part 21 records will be in accordance with 10 CFR Part 50 requirement The Part 21 document has been posted at the facilit Discussions with plant personnel revealed that no system exists fer the tracking and =aintaining of Part 21 reports and docu=entation generated by the licensee's contracters and subcontractor The inspector stated that this item will be reviewed during a subsequent II inspection.

i i

No items of nonce =pliance cr deviations were identified.

i l Review of Plant Ocerations i The inspector reviewed facility operations to ascertain whether I they are in confor:ance with Techt.ical Specification requirements, i 10 CFR require =ents and in accordance with ad=inistrative pro-

[ cedures. The inspection included reviews of selected operating

'

legs, daily orders, ju=per legs, licensee deviation reports and a cour of the facility.

i

!

I - L-i l

l t

l l

l

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

,

. .

.

.. .

.

The following records were reviewed: Units 1 and 2 control rocm logs for April, May, June and

July 197 Daily Crder 3cok for April, May, June and July 197 Jumper Log for the period April to July 197 Deviation Reports D4-1-77-25 to D4-1-77-56 for Unit 1 and D4-2-77-25 to Dr-2-77-45 for Unit A plant cour of the Units-1 and 2 areas determined that monitoring instrumentation is recording as required, radiation controls are being properly implemented, plant housekeeping conditions are adequate, existence of fluid leaks have been identified and are being properly controlled, pipe hanger / seismic restraint settings and oil levels are normal, valve positions and equipment start switches are as required, equipment caution and out-of-service tag control is proper, responses to control room annunciators are adequate, and control room manning is in confor=ance with 10 CFR 50.54(k) and facility-Technical Specification . Office Review of Licensee Event Reports The inspector reviewed licensee's event reports to ascertain whether corrective actions discussed in the reports appear appropriate and whether infor=ation reported to the NRC satisfies reporting require-ments. The felicwing event reports were reviewed and are censidered-closed:

Unit 1 l R0 78-16/03L dated June 26, 1978, " Vacuum Breaker 1601-33E 'Jould Not Close."

RO 78-13/03L dated July 14, 1973 "Lew-Low Reactor Level Sw1:ch Failed."

RO 72-20/03L dated July 7,1978, "Drywell Equipment Su=p Discharge Valve Incperable."

10. Site Review of Licensee Even Reper:s l

l Licensee Event Reports were reviewed to verify tha: de: ails were accurately repor:ed; :ha: the cause was iden:ified; that :he even:

was reviewed and evalus:ed in accordance vi:h Techni:a1 Spe if t:aciens; and :he corrective ac:icn was :aken as described in :he repcrt. The j folleving LER's were reviewed and are censidered clesed:

!

-5-

,

(s=

. . .

e'

e No items of noncompliance or deviations were identified

, Unit 1

r - RO 78-18/03L dated July 14, 1978, " Low-Low Reactor Level Switch

. Malfunctioned." On June 15, 1978, while performing reactor water level fimccional testing, switch LIS-1-263-72A failed to cperate as required. Failure of the switch'is attributed to instrument setpoint drift cause by magnet misalignment. The inspector verified that the switch was adjusted and ratested satisfactoril Unit 2 RO 78-20/03L dated May 8 and 16, 1978, "RCIC Inboard Steam Inlet Valve Inoperable." On April 9,1978, while performing monthly valve operability tests, valve 1301-16 would not clos Cause of the problem is attributed to torque switch failur *

The inspector verified that the valve was made operable and also confirmed that t modification has been initiated to the valve control circuit to preclude valve closure if a torque switch failure occur . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

on August 11, 1978. The inspector su=narized the scope and-findings of the inspectio With regard to the =aintenance of Part 21 records, the licensee stated that this matter would be reviewed.

.h-