IR 05000244/1980003
| ML17250A410 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/27/1980 |
| From: | Dante Johnson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17250A407 | List: |
| References | |
| 50-244-80-03, 50-244-80-3, NUDOCS 8007210165 | |
| Download: ML17250A410 (10) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
w Report No.
50-244/80-03 Docket No.
50-244 License No.
DPR-18 Priority Category Licensee:
Rochester Gas and Electric Cor oration 89 East Avenue Rochester New York 14649
'Facility Name:
R.
E. Ginna Nuclear Power Plant Inspection At:
Ontario New York Inspection. Conducted:
A r 1 21-25 1980 Inspectors:
n, eac or nspec or a e t
L Approved by:
er, se
,
eac or rogec s
ection No. 4, ROMANS,Branch a e Ins ection Summar:
Ins ection on A ril 21-25 '980 (Re ort No. 50-244/80-03)
Areas Ins ected:
Routine, unannounced inspection of refueling and outage activi-les, inc u sng preparations for,.-refueling and previous inspection findings.
The inspection involved,32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> on-site.,by one regionally'based inspector.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 1977)
~OVa v n/W<
5
OETAILS 1.
Persons Contacted 2:
Mr,. F. Aman, Office Supervisor Mr. W. Backus, Operations Supervisor Mr. L. Depew, Shift Supervisor Mr. T. Marlow, Outage Coordinator
- Mr. R. Morrill, Training Coordinator
- Mr. J.
Noon, Assistant Plant Superintendent
- Mr. B. Snow, Plant Superintendent The inspector also interviewed other licensee and licensee contractor per-sonnel including members of the operations, health physics, refueling, maintenance and general office staff.
- Oenotes those present at exit interview.
Licensee Action on Previousl Identified Item (Closed)
Unresolved Item (80-04-02):
The inspector verified by review of applicable records and interviews held with licensee personnel that all licensed operators have received training in emergency procedures E. 1.1 through E. 1.4.
The training was presented in the form of discussion and control room walk-throughs of the procedures.
3.
Pre arations for Refuelin a.
Refuelin Procedure Review The licensee has reviewed, approved and issued Refueling Procedure No. RF-55, Cycle IX-X Refueling, Revision 0, dated April 9, 1980, which provides instructions for fuel transfer and core verification, recycled fuel inspections, and general conduct of refueling operations.
These procedures, which were prepared by the licensee's contractor, were reviewed by the inspector on-site.
No items of noncompliance were identified.
b; New Fuel-'Recei't and Ins ection The inspector reviewed the quality assurance documentation associated with the release for shipment, shipment, and receipt of the
new fuel assemblies and the 4 mixed oxide assemblies for the cycle IX-X reload.
The documentation confirmed that the fuel met the-technical
and quality assurance requirements of the licensee's purchase order and associated specifications of the fuel supplier.
Receipt inspections were conducted at the licensee's facility in accordance with gCIP-3.4,
"Receiving Inspection of New Fuel", Revi-sion 2, dated March 3, 1979.
Records of detailed inspections for all fuel assemblies received were reviewed.
No items of noncompliance were identified.
4.
Refuelin Activities Pre-Fuel Handlin Activities The licensee had completed reactor vessel head and internals removal during the period of April 1-15, 1980 in preparation for refueling.
The inspector reviewed the completed procedures and associated data listed below to confirm, on a sampling basis, that pre-fuel handling activities were properly accomplished.
The following procedures were reviewed:
RF-2A, Requirements for Reactor Head Removal; RF-2B, Required Valve Lineup for Reactor Head Removal; RF-20, Filling the Refueling Canal; RF-8.0, Fuel Assembly and Core Component Movement Prerequisites and Precautions; RF-10, Fuel Handling System Checkout and Demonstration Procedure; RF-1.1, Refueling Organization; RF-5, Limitations and Precautions for Handling New and Partially Spent Fuel Assemblies; RF-7, Handling of New Fue'l Assemblies and RCC Elements The procedures documented that surveillance testing and prerequisite verification required prior to fuel handling had been satisfactorily accomplished, including:
Technical Specification Section 3.2, 3.8, 3. 11 and 4. 11 requirements; Refueling machine operation;
Ventilation system operation and alignment; Refueling interlock checks; Crane testing;,
Containment and spent fuel pool ventilation and radiation monitor verifications; Communication system operability; and; Spent. fuel cooling capability.
No items of noncompliance were identified.
b.
Fuel Handlin Activities The inspector verified by direct observation and record review that fuel handling activities were being conducted in accordance with approved procedures and Technical Specification requirements.
The following areas were inspected:
(1)
Core subcr'itical monitoring during refueling and suspension of fuel shuffle activity.
(2)
Core shutdown margin established by maintaining a boron concen-tration of at least 2000 ppm in the reactor cavity, RHR'ystem and spent fuel pit.
(3)
Fuel manipulations over the core and spent fuel pit, as well as fuel transfers from the reactor cavity to the spent fuel pit, were conducted in accordance with refueling procedures.
(4)
Fuel accountability was maintained in accordance with RF-55.
(5)
Refueling area housekeeping was controlled to prevent loose articles from falling into the reactor cavity and spent fuel pool.
(6)
Core internal and reactor vessel components/equipment were stored properly to protect against damage.
(7)
Refueling crew staffing conformed with procedure RF-55 and Technical Specification requirements.
(8)
Reactor cavity and spent fuel pool water level and temperature were maintained as required by Technical Specification (9)
An SRO with no other concurrent duties supervised all fuel handling activities in the containment.
(10)
Communications were maintained between the control room, the spent fuel pool area, the refueling bridge operator and the fuel transfer carriage operator as required by procedure.
(11)
Containment and auxiliary building integrity and ventilation were maintained as required.
No items of noncompliance were identified.
c.
Fuel Shuffle Witnessin The inspector witnessed refueling activities in the control room, containment and the spent fuel pool area during the day and afternoon shifts on April 22 and 23, 1980.
Approved refueling procedures were available and in use by refueling personnel, and fuel status boards were maintained as required during fuel movement.
Minor difficulty was experienced.with.periodic noise problems on one source range channel, resulting in an intermittent increase in channel output during fuel assembly insertion into 'the core.
Refueling personnel-.
suspended core loading during periods when channel output was ques-tionable:
Investigation by I8C personnel could not identify any cause for the problem.
The inspector noted the increase in source range channel. output -was erratic and would occur at times when fuel was not being loaded into the core.
The inspector also observed that during loading of assemblies with core locations between the channel and a source assembly the channel responded normally to subcritical multiplication.
No items of noncompliance were identified.
5.
Exit Interview A management meeting was held with licens'ee personnel (denoted in paragraph 1)
at the conclusion of the inspection.
The purpose, scope and findings of the inspection were discusse /