IR 05000254/1978028
| ML19261B897 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/09/1979 |
| From: | Chrissotimas N, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19261B891 | List: |
| References | |
| 50-254-78-28, NUDOCS 7903070513 | |
| Download: ML19261B897 (5) | |
Text
.
.
.
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGIO" III Report No. 50-254/78-28; 50-265/78-29 Docket ho. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60630 Facility Name: Quad-Cities Nuclear Power Station, Units 1 and 2 Inspection At: Quad-Cities Site, Cordova, Illinois c
Inspection Conducted: November 16-17, 21-22; and December 6-7, 13, and 14, 1978
,
.
t
.
{.< a <
-
Inspector:
'.. J / hrissotimos
/ '/ /
C
n'.
.jA',, g'
'
N
'
,/
Approved By: R. C. Knop, Chief
'.
,
Reactor Projects Section 1 Inspection Summary Inspection on I;ovember 16-17, 21-22; and December 6-7, 13, and 14, 1978 (Report No. 50-254/78-28; 50-265/78-29)
Areas Inspected:
Routine, urannounced inspection of organization and administration, procedures review of licensee event reports, followup on outstanding in,cactie-items, and plant t'ur.
The inspection involved 61 manhours of inspection by one NRC inspector.
Results: No itens of noncompliance or deviations were identified.
7903 070 T'l'3
.
.
.
.
Commonwealth Edison-2-Company JMN ] 51979 k'e will gladly discuss any questions you have concerning tliis inspection.
Sincerely, 1 0.47 Gaston Fiorelli, liie f Reactor Operations and Nuclear Support branch Enclosure:
IE Inspection Report No. 50-254/78-28 and No. 50-265/78-29 cc w/ encl:
?!r. N. Kalivianakis Station Superintendent Central Files Reproduction Unit NRC 20b PDR Local PDR NSIC
/ TIC Anthony Roisaan, Esq.,
Attorney Dean Hansell, Office of Assistant Attorney General
.
.
.
.
DETAILS 1.
Persons Contacted
- N. Kalivianakis, Station Superintendent J. Gudac, Assistant Superintendent L. Gerner, Technical Staff Supervisor T. Tamlyn, Lead Operating Engineer R. Bax, Operating Engineer, Unit 2 G. Conschack, Operating Engineer, Unit 1
- R.
Flessner, Assistant Technical Staff Supervisor R. Spear, Maintenance Engineer
- J.
Heilman, Quality Assurance Engineer, Operations The inspector also interviewed several other licensee employees including shift engineers and foremen, reactor operators, technical staff personnel, and quality assurance and control personnel.
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Open Item (50-254/76-21; 50-265/78-22): Determination of rated power for SBGT heater operability. The inspector verified that a procedure change has been completed to clarify when rated power conditions are met.
(Closed) Open Item (50-254/78-19; 50-265/7o-20): A system for tracking and maintaining Part 21 reports did not exist. The inspector verified that a program for tracking Part 21 reports is described in the Quality Assurance Manual.
(Closed) tioncompliance (254/75-30; 265/76-29):
Failure to adhere to procedures. The inspector verified that the following changes had been made to handle station drawing: procedures QDM-7 and QP6-51 have been revised.
2.
Procedures The inspector reviewed station procedures to ascertain whether changes made to these approved procedures are in conformance with regulatory requirements and whether the technical adequacy of reviewed procedures is consistent with the intended mode of-2-
.
.
.
.
operation. The following were verified during this review: review and approval of permanent and temporary procedure changes was in accordance with technical specifications; temporary procedures do not conflict with technical specifications; procedure changes were made to reflect technical specification revisions; changes made to procedures were in conformance with 10 CFR 50.59 requirements and records of these changes are maintained as required: control room procedures were current; and the technical content of procedures is adequate to control safety related operations within regulatory requirements.
No items of noncompliance or deviations were identified.
3.
Organization and Administration A review of the licensee's onsite organization structure was conducted to determine the personnel qualification levels are in conformance with the technical specifications, authorities, and responsibilities are as delineated in the technical specifications, operating crew composition and the license personnel requirements are in compliance with the technical specifications onsite and offsite review committee membership qualifications are satisfactory, and licensee organization and structure changes have been reported to the NRC.
No items of noncorpliance or deviations were identified.
4.
Office review of Event Reports The inspector reviewed licensee's event reports to ascertain whether corrective actions discussed in the reports appear appropriate and whether information reported to the NRC satisfies reporting requirements. The following event reports were reviewed and are considered closed:
RO 50-254/76-29/03L, dated October 25, 1978:
Snoke detectors replaced with fire detector / suppression system.
RO 50-254/78-30/03L, dated October 26, 1978:
Dual positicn indicated for suppression chamber to drywell vacuum breaker.
RO 50-254/78-09/03L, dated March 20, 1978:
" Obstruction in sensing lines.
-3-
e
.
,
.
5.
Site Review of Licensee Event Reports Licensee event reports were reviewed to verify that details were accurately reported; that the cause was identified; that the event was reviewed and evaluated in accordance with technical specifica-tions; and the corrective action was taken as described in the report. The following LER's were reviewed:
RO 50-265/78-26/03L, dated September 20, 1978:
"A" RHR room water-tight door found open. The inspector verified that corrective action was completed and warning signs are posted.
RO 50-265/78-32/03L, dated September 29, 1978: Main steam target rock pressure relief valve failed to open. The inspector verified that corrective action was complete and retesting proved operability of the relief valve.
RO 50-265/78-33/03L, dated Septenber 30, 1978:
Two snubbers found inoperable.
Routine hydraulic snubber surveillance revealed that two snubbers were inoperable. Thb inspector confirmed that corrective action was completed.
RO 50-265/78-34/03L, dated October 2, 1978: Control ROD failed to scram upon receiving a test signal. The cause of this event is attributed to the malfunction of the scram solenoid valve. The inspector confirmed that the licensee has initiated a preventive maintenance program to overhaul all the scram solenoid valves.
In regards to RO 50-254/78-21/03L, dated July 18, 1976:
RO 5 0-265/78-27/03L, dated July 17, 1978; and RO 50-265/78-36/03L, dateu October 16, 1978; which involve setpoint drift of mercoid switches.
Immediate corrective action to adjust the trip points within limits is adequate. However, Action item Record 7-75-25 is referenced as pe rmane nt corrective action.
This action item has been in existance for three years and no resolution has evolved. Reference to Action item 4-75-25 as permanent corrective action is inadequate and the inspector stated that this item will be reviewed during subsequent lE inspections.
6.
Independent inspection Effort The inspector spent approximately 20 percent of the inspection time pursuing activities outside the defined inspection progran.
This included: The re-examination of key procedures, examination of response to annunciator, general annuciator attention and plant tours. The inspector noted control room cleanliness is adequate considering work presently being performed.
-4-
a
-
.
.
.
No items of noncompliance or deviations were identified.
7.
Exit Interview The inspector met with licensee representatives (Denoted in Paragraph 1) on December 14, 1978. The inspector summarized the scope and findings of the inspr,: ion and comments in regards to Action Item 4-75-25.
The licensee acknowiedged the inspector's commentt>.
-5-