IR 05000309/1980001
| ML19309E257 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/21/1980 |
| From: | Lazarus W, Martin T, Swetland P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19309E245 | List: |
| References | |
| 50-309-80-01, 50-309-80-1, NUDOCS 8004210053 | |
| Download: ML19309E257 (1) | |
Text
- _ _ _ _ _ _ _.
.
.
.
.
.
O U.S. NUCLEAR REGULATORY COMMISSION
'
-
0FFICE OF INSPECTION AND ENFORCEMENT Region I 50-309/80-01 Report No.
Docket No. 50-309 DPR-36 C
--
License No.
Priority Categery Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name: Maine Yankee Nuclear Power Station Inspection at: Wiscasset, Maine Inspection conducted: January 21-25, 1980 Inspectors:
A c#/h//fd W. J. Lazarus, Rea r Inspector
'date signed
cR/b?/ M P. D. Swetland, Restor Inspector date signed date signed Approved by:
cRI?/Id T. T. Martin, Chief, Reactor date signed Projects Section No. 3, RO&NS Branch Inspection Summary:
Inspection on January 21-25, 1980 (Report No. 50-309/80-01)
Areas Inspected:
Routine unannounced inspection of refueling preparation; refueling activities; plant operations; licensee performance of review and audits and followup on selected Licensee Event Reports (LERs).
The inroection involved 38 inspection-hours on site by two region-based inspectors.
Results: Two items of noncompliance were identified.
(Infraction -
,
Failure to comply with Radiation Work Permit requirement - paragraph
-
3.b.
and Infraction - Audible count rate monitor not operating in refueling cavity area - paragraph 3.b.).
Region I Form 12
'
(Rev. April 77)
800421o o 5 7 l
.
.
DETAILS 1.
Persons Contacted P. Anderson, Administrative Department Head R. Arsenault, Assistant Operations Department Head
- G. Cochrane, Plant Health Physicist
- C. Frizzle, Assistant Plant Manager J. Hebert,' Plant Engineering Quality Assurance Group
>
Supervisor
- W. Paine, Operations Department Head R. Radasch, I and C Departnent Head l
S. Sadosky, QC and Audit Coordinator D. Sturniolo, Chemistry and HP Departnent Head The inspector also interviewed several operators and other members of the technical and adninistrative staffs.
- denotes those present at the exit interview.
2.
Licensee Action Concerning Previous Inspection Findings (Closed) Followup Itsu (309/79-17-01) The inspector reviewed temporary
,
procedure 4-44, " Matrix Relay Testing", and completed test documentation for tests performed on 12/27/79,1/10/80, and 1/13/80.
3.
Preparation for Refueling
-
f a.
Approved Procedures Available for Use The inspector reviewed licensee procedures to verify that approved procedures were available for:
New fuel receipt and inspection
-
Fuel transfer
-
'
Core loading and verification
-
Recycled fuel inspection and sipping
-
I
.-
l
3 i
Fuel bundle reconstitution
'
-
Refueling equipnent operation
-
No inadequacies in procedural coverage were identified.
b.
New Fuel Receipt Inspection The inspector reviewed documentation of receipt inspections for fuel containers numbered 6457, 6253, 6249, 6449, 6463, and 6227 to verify that required inspections were conducted in accordance with license procedures and that discrepancies were satisfactorily resolved.
No items of noncompliance were identified.
4.
Refueling Activities a.
Pre-Fuel Handling Activities The inspector reviewed documentation of canpleted surveillance tests listed below to verify that required pre-fuel handling tests had been completed.
3.1.10, Refueling Interlocks, Completed 1/20/80
-
3-6.2.2.1.29, Source Calibration of the Radiation Monitoring
-
System (Fuel Pool Platform completed 1/11/80, Manipulator Crane
,
completed 1/14/80).
'
3-6.2.2.17, Daily RMS Operational Test, (Ventilation system
-
trips, completed 1/14 - 22/80)
13-6, Manipulator Crane Position Indication Alignment, completed
-
1/20/80 10-1, Core Reloading Maine Yankee Reactor (Section 3, Initial
-
Conditions completed)
No items of noncompliance were identified.
,
l l
.
-
-. _ - - __
_________ __ ___________________ ____
,
.
'
,
i b.
Observation of Fuel Handling Activities i
The inspector observed fuel handling operations in the refueling cavity, spent fuel pool, and the Control Room frequently during this inspection, including portions of all three shifts.
The following items were reviewed.
Proper core monitoring performed
-
'
Fuel handling, fuel accountability and sipping conducted
-
in accordance with approved procedures r
Core internals stored to protect from damage
-
Housekeeping and cleanliness conditions acceptable
-
Proper make-up and qualification of refueling crews
-
Refueling Cavity and Spent Fuel Pool water level as
-
required by Technical Specifications Baron concentration (shutdown margin) as required by
-
Technical Specifications Constant direct communication maintained between the
-
Control Room and fuel handling personnel when core alterations were in progress
.
Boric Acid Storage Tank level as required by Technical
-
Specifications RHR flow maintained to Refueling Cavity as required by
-
Technical Specifications Audible count rate monitoring functioning in the Refueling
-
Cavity Area and Control Room
Radiation protection requinnants were being met
-
Fuel Building ventilation lineup as required by Technical
-
Specification 3.13.C l
l l
i
!
_ _.
._
.
.
.
l
i
!
Except as noted below, no items of noncompliance were identified.
,
During observation of fuel handling operations on the third j
shift, January 21, 1980, the inspector noted that the source
!
range audible count rate monitor was not operating in the re-i fueling cavity area during core alterations as required by
Procedure 10-1, " Core Reloading", and Technical Specification - 5.8.
Corrective action was taken to increase the volume of the audible neutron count rate and was found acceptable during i
a subsequent inspection of the refueling cavity area prior to
-
completion of the inspection.
This item is an infraction (309/80-01-01).
I i
During observation of activities in the refueling cavity on j
the same shift, the inspector noted that the refueling machine
!
operator was not wearing cotton gloves as required by Radiation i
Work Pennit 80-1-465 of January 21, 1980, procedure 9.1.10,
" Radiation Work Permits", and Technical Specification 5.8.
Corrective action was taken and reinspected prior to the end
of the inspection and found to be acceptable.
This item is an i
infraction (309/80-01-02).
5.
PORC and NSARC Review Functions I
The Plant Operations Review Comittee (PORC) and Nuclear Safety
Audit and Review Committee (NSARC) review functions were reviewed i
by the inspector to verify that:
l
,
!
-
All PORC and NSARC meetings were convened during the previous
year at the frequency required by the Technical Specifications;
'
The meeting membership of PORC and NSARC meetings satisfied
-
i the quorum requirements of the Technical Specifications;
Noncompliances with Technical Specfications or rules and
-
regulations were reviewed as required by the Technical Specifications; i
l Plant procedures were reviewed as required by the Technical
-
,
Specifications; I
!
Proposed changes to Technical Specifications were reviewed as
-
required by the Technical Specifications; i
,
!
-
-
- -
_
.
.-
...
_-
-. _ _ _ _
_ _.
_ _ __
. -.
t
,
.
-
,
i l
!
!
i
'
The review included discussions with licensee personnel and review of the Technical Specifications and the following plant records.
!
Minutes of PORC Meetings (all 1979 meetings)
-
Minutes of NSARC Meetings (all 1979 meetings)
l
-
No items of noncompliance were identified.
6.
Licensee Event Report (LER) Followup The inspector reviewed LERs received in RI office to verify that details of
,
the event were clearly reported including the accuracy of the description of cause and adequacy of corrective action.
The inspector also detemined
!
whether further infomation was required from the licensee, whether generic i
implications were indicated, and whether the event warranted on site followup.
l During on site followup, the inspector verified that reporting requirements
!
of Technical Specifications and Regulatory Guide 1.16 had been met, that appmpriate corrective action had been taken, that the event was reviewed
by the licensee as required, and that continued operation of the facility
!
was conducted within Technical Specification limits.
The review included l
discussions with licensee personnel, review of PORC meeting minutes, Plant
-
Infomation Reports (in-house reports), and applicable logs.
The following
!
LERs were reviewed.
79-29/99X-0 and 79-30/99X-0, High Dose Equivalent Iodine-131 in the
-
'
[
The inspector reviewed RCS chemistry records for the period December 10, 1979 - January 21, 1980 to check the trends of the concentration of the iodine isotopes. The inspector also witnessed the fuel sipping operation being perfomed in the Spent Fuel Pool.
At the time of the inspection a j
small number of the sampled fuel assemblies indicated failed fuel pins.
A
further report will be submitted to the NRC upon completion of the fuel l
inspection.
,
79-31/32, Failed RPS Matrix Relays f
-
The inspector reviewed the results of test procedure 4-44, " Matrix Relay as noted in detail two to verify that the two matrix relays that Testing"(AC-1 and BD-3) would not have prevented a reactor trip.
failed Followup inspection in this area covering the increased test frequency will continue until the substitute relays have been procured and installed.
(309/80-01-
03)
.
!
!
,
.
.
i 7.
Reactor Coolant Cystem High Chloride Levels
During a review of Reactor Coolant System Chemistry logs and discussions l
with a plant chemist, the inspector noted abnormally high chloride concentration in the reactor coolant (as high as 3 ppm).
The logs indicate that the chloride intrusion occurred after the plant was in cold shutdown and did not represent a violation of a limiting condition for operation. Additional followup on this item will be
,
performed in a subsequent inspection to review the cause, status of cleanup which must be complete prior to starting up, and steps taken to prevent recurrence.
(309/80-01-04)
6.
In-Office Review of Periodic Reports
!
The inspector reviewed the November and December 1979 Monthly Operating Reports received in the RI office to verify that reporting requirements were met.
No inadequacies were identified.
9.
Exit Interview l
The inspector met with licensee representatives (see detail 1 for attendees) at the conclusion of the inspection to discuss the scope and findings of the inspection as detailed in this report.
i i
I e
i i
i i