IR 05000010/1978001
| ML19340A661 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/17/1978 |
| From: | John Baker, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A659 | List: |
| References | |
| 50-010-78-01, 50-10-78-1, 50-237-78-01, 50-237-78-1, 50-249-78-01, NUDOCS 8009020601 | |
| Download: ML19340A661 (4) | |
Text
.
A)
.
.
'
pJ
~
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
-
n
~
REGION III
Report No.:
50-10/78-01; 50-237/78-01; 50-249/78-01 Docket No.: 50-10; 50-237; 50-249 License No. DPR-2, 19, 25 Licensee:
Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility name: Dresden Nuclear Power Station, Units 1, 2, and 3 Inspection at: Dresden Site, Morris, IL Inspection conducted: December 29-30, 1977 and January 4, 1978 SA Inspector:
/ 7 A
i
<
-
Approved By:
W.
S.
i
/ /
- 3
'
'
Nuclear Support Section
-
Inspection Summary Inspection on December 29-30, 1977 and January 4, 1978 (Report No.
50-010/78-01; 50-237/78-01; 50-247/78-01)
Areas Inspected: Routine, unannounced inspection of licensee action on previous inspection findings, licensee program of Unit 1 control rod blade replacement, Unit 3 shutdowr. margin determination, startup testing af ter a refueling outage, and review of plant operations. The inspection involved 23 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
.
300so2o
m
'
>
,
r,
DETAILS
'
i
-
1.
Persons Contacted
- B. Stephenson, Station Superintendent
- A. Roberts, Assistant Station Superintendent
- B.
Shelton, Administrative Assistant
- D. Farrar, Technical Staff Supervisor
- J. Kolonowski, Unit 2 Operating Engineer
- T. Rausch, Lead Nuclear Engineer
- G. Reardanz, Quality Assurance Inspector, Operations
- R. Kyrovac, Quality Control W. Hildy, Instrument Engineer The inspector also contacted several other licensee employees, including staff engineers, refueling foremen, shift engineers, shif t foremen, and Nuclear Station Operators.
- Denotes those present at exit inte rview.
2.
Licensee Action on Previous Inspection Fir ttngs
.
(Closed) Noncompliance (50-237/77-04):
Failure to have a detailed
-
written procedure for the calibration of LPRM's experiencing seal failures. The inspector verified that procedures had been implemented which stated criteria for seal failures, when LPRM's would be bypassed, and calibration steps before LPRM reinstatement.
(Closed) Noncompliance (50-237/77-04):
Failure to adhere to an approved procedure in that the power normalization factor for a LPRM calibration was not recorded. The inspector verified that the licensee had re-emphasized the importance of following procedures to the letter to the members of the Nuclear Engineering Group.
3.
Unit 1 Control Rod Blade Replacement The inspector reviewed the licensee's program for tracking exposure to each control rod blade and determination of criteria for blade replacement or movement to an area of lower expected flux levels until replacement could be effected.
No items of noncompliance or deviations were identified.
-2-
~
,
.
4.
Unit 3 Shutdown Margin Determination
-
y The inspector verified that the licensee was ensuring adequate
-
shutdown margin throughout the operating cycle. That the calculation
-
of the reactor shutdown margin was technically correct and in accordance with the facility's technical specifications, and that the shutdown margin determination was performed at the frequency required by the facility's techn. cal specifications.
No items of noncompliance or de.*iations were identified.
5.
Startup Testing-Refueling, Unit 2 The inspector verified that startup testing was conducted in accordance with approved procedures and that the facility is being operated in conformance with NRC requirements and licensee procedures.
The inspector verified that the licensee had conducted or had plans to conduct control rod drive friction and scram tests, control rod sequence and reactivity checks, core power distri-bution limits checks, calibration of LPRM;s, calibration of APRM;s, core thermal power determinations, and reactor shutdown margin determinations.
The inspector reviewed procedures and test results for control rod drive friction and scram tests, control rod sequence and reactivity checks. APRM calibrations, and shutdown margin determinations and verified that the refueling outage
,
startup testing was conducted in accordance with technically adequate procedures and within license limits.
No items of noncompliance or deviatior.s were identified.
6.
Review of Plant Operations, Unit 2 The inspector verifie. that systems disturbed or tested during the refueling ontage were returned to an operating status prior to plant startup, that controd rod withdrawal sequence and rod withdrawal authorizations were available and in effect prior the startup af ter refueling, and that surveillance tests were performed during the refueling ontage as required by Technical Specifications.
During his review of the licensee's startup package for December 1977 the inspector noted six (6) examples of temporary changes made to check off/ valve lineup sheets not in accordance with Technical Specifications 6.2.D (DOP 300-M1, " Control Rod Drive Hydraulic System;" DOP 700-E2, " Intermediate Range Monitoring;"
DOP 1500-El, "LPCI Power Supply Checkoff;" DOP 3200-M1, "Feedwater System;" DOP 5400-M., " Steam Jet Air Ejector and Offgas Systems;"
-3-
._
.
s
.
,
o and DOP 5400-M2, " Unit 2 Offgas System - Filter Building Valve
.
- "i.
Checkoff List").
He also noted there had been no shift engineer / shift
"
\\
foreman review of ten (10) checkoff / valve lineup sheets (DOP 300-M1,
" Control Rod Drive Hydraulic System;" DOP 1500-M1, "LPCI and Contain-ment Cooling;" DOP 2300-M1, "HPCI," DOP 3200-M1, "Feedwater System;"
DOP 3500-M1, "Feedwater Heater Extraction Steam, Vents, Drains, and Drainage;" DGP 1-1, " Unit 2/3 Normal Unit Startup;" DOS 1500-3,
" Containment Cooling Service Water System Quarterly Check Sheet;"
DOS 1400-1, " Core Spray System Pump Operability with Torus Available;"
DOS 1400-2, " Core Spray Valve Operability Check;" and DOS 1500-1,
"LPCI System Valve Operability Test "). The licensee had been cited for two items of nunc: mpliance in Inspection Report No. 50-010/77-32 for noncompliance witn Technical Specification 6.2.D and 6.2.A (failure to make proper temporary procedure changes and failure to adhere to an approved procedure). Since the corrective action implementation date was December 30, 1977, and the occurences exemplified above happened during November and December,1977, it is technically inappropriate to issue apparent items of noncom-pliance for recurrence before corrective action is ef fected. They are of considerable concern to the inspector in that they are further examples of the failure of lower management overview of reactor operations.
No items of noncompliance or deviations were noted.
'
_
7.
Exit Interview The inspector met with licensee representatives (denoted in Para-
,
graph 1) at the conclusion of the inspection on January 4,1978 and summarized the scope and findings of the inspection.
f i
t'
-4-
i
.l
,.