IR 05000277/1980007
| ML19312E257 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/18/1980 |
| From: | Bettenhausen L, Caphton D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19312E256 | List: |
| References | |
| 50-277-80-07, 50-277-80-7, NUDOCS 8006030612 | |
| Download: ML19312E257 (4) | |
Text
.
.
.
U. S. NUCLEAR REGULATORY COMMISSION h
0FFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No. _ 50-277/80-07 Docket No.
50-277 License No.
DPR-44 Priority Category _
C
--
Licensee:
Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Peach Bottom Atomic Power Station, Unit 2 Inspection At:
Delta, Pennsylvania Inspection Conducted:
March 28-April 2, 1980 Inspectors:
h A7M-Y//'7/86
'
L. H. Bettenhausen, Ph.D.. Reactor Inspector date date date Arproved by:
Y dd.
/P PC D. L. Caphton, Chief, Nuclear Support
'dtte (
Section No.1. RO&NS Branch Inspection Summary:
Inspection on March 28-April 2, 1980 (Unit. 2, Report No. 50-277/80-07)
Areas Inspected:
Routine unannounced inspection of refueling activities, prerequisites for refueling and fuel handling.
The inspection involved 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> on site by one regional based NRC inspector.
Re$ults: No items of noncompliance were identified during the conduct of this Kspection.
.
e c c e sj e (= A Region I Form 12 (Rev. April 1977)
-
t
__
_ _ _ _ _ _
- - - - - - - - - - - - - - - - - - - - - - - - - - - -,
-
.
.
-
DETAILS 1.
Persons Contacted K. Hunt, Computer Engineer F. Polaski, Reactor Engineer
- S. Spitko, Quality Assurance Engineer W. Tilton, Fuel Floor Supervisor
- W. Ullrich, Plant Superintendent J. Yacyshyn, Surveillance Test Coordinator
- C. Cowgill, USNRC Resident Inspector The inspector also contacted other maintenance, health physics, operations
-,
and engineering staff members in the course of this inspection.
- Present at the exit interview on April 2,1980.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 277/78-32-02:
Computer printout record management.
The Reactor Engineer now obtains and maintains a continuous chronological file of periodic and demand computer printouts. Specific data requests are met by obtaining a second computer copy or a xerox copy of the printouts.
(Closed) Unresolved Item 277/78-32-03: Surveillance procedures reference computer printouts from which data is extracted.
Procedures now reference or attach copies of data upon which the surveillance acceptability is based.
(Closed) Inspector Followup Item 277/78-32-04: Surveillance procedure ST 3.7-2 contained an equation whose origin was obscure.
The procedure has been simplified; the equation has been deleted.
The inspector had no further questions on these items.
3.
Pre-Refueling Activities, The inspector reviewed the following procedures required to be completed before operat-lon of the refueling bridge:
FH 21.1,1, Startup of Refueling Platform, Rev. O, approved October 23,
--
1975, completed February 11, 1980.
FH 21.1.2, Checkout of Refueling Platform Bridge, Trolley, Monorail,
--
and Hoists in the Fuel Pool, Rev.1, approved April 2,1976, completed March 21, 198 _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ - - - _ _ _ _ _ _ _ _ - - - _ - _
_
. -. -
.
- _ -
.
FH 21.1.3, Checkout of Refueling Platform Hoist and Load Cells, Rev. 1,
--
April 2, 1976, completed March 21, 1980.
FH 21.1.6, Checkout of Air _ Compressor, Air Lines and Solenoid Valves,
--
Rev. 1, approved April 2, 1976, completed March 18, 1980.
FH 21.1.7, Checkout of Refueling Platform Bridge, Trolley, Monorail
--
and Hoists in the Reactor Cavity, Rev. 1, approved April 2, 1976, com-pleted March 21, 1980.
M4.20, Refueling Platform Electrical Inspection, Rev. 4, approved
--
January 18, 1980, completed February 11, 1980 and the following completed procedures for standby gas treatment operability and secondary containmant integrity:
ST 13.7 Standby Gas Treatment Filter Differential and Heater Capacity,
--
'
rain d nd ra n ST 13.9 Secondary Containment Capability Test, Rev. 6, approved
--
November 1, 1979 and completed March 11, 1980.
,
The inspector had no further questions about refueling machine operability or secondary containment.
Refueling interlocks are demonstrated satisfactory by performance of ST 12.1, Refueling Interlock Functional Test.
The inspector reviewed results of the test performed March 26, 1980/1145PM, prior to refueling operations.
The inspector identified no items of noncompliance with regard to pre-fuel-handling activities.
4.
Fuel Handling Activities The inspector verified by direct observation that fuel handling activities were being conducted in accordance with FH-6C, Fuel Movement and Core-Altera-tion Procedure During a Fuel Handling Outage, Rev. 9, approved January 14, 1980.
The inspector observed steps 332-336 and 412-424 of this procedure on the refueling floor and steps 511-527 in the Control Room.
Observation included core monitoring by the Assistant Control Operator using Source Range Monitors, removal of fuel bundles from the core and placement in the spent fuel pool, accountability, housekeeping, communications between refueling floor and control room, crew staffing, direct supervision by a Senior Reactor Operator with no other duties and proper vessel water level maintained.
The inspector has reviewed ST 3.1.2, SRM Core Monitoring Test, Rev. 3,
,
approved August 14, 1979, for the dates March 26, 1980, March 27, 1980,
.
_
.
.
_. _ _ _. __
Q-e
March 28, 1980, March 29, 1980, March 30, 1980, March 31, 1980 and April 1, 1980.
This test is used as the daily check of SRM operability; the test results accurately reflected conditions of the cora and the identified and subsequently corrected problems with SRM "8".
The inspector also observed security and health physics on the refueling floor and a welding / cutting operation conducted under administrative pro-cedure A-12, Ignition Source Control Procedure, Rev. 1, April 21, 1978.
No items of noncompliance or deviations were identified.
5.
Exit Interview At the conclusion of this inspection on April 2, 1980, the inspector reviewed the scope and presented the inspection findings with licensee management identified in paragraph 1.
I l