IR 05000338/1985034
| ML20136J291 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/30/1985 |
| From: | Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20136J273 | List: |
| References | |
| 50-338-85-34, NUDOCS 8601130316 | |
| Download: ML20136J291 (4) | |
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>P itioq'o UNITED STATES NUCLEAR REGULATORY COMMisslON
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101 MARIETTA STREET, N.W.
ATLANTA, GEORGI A 30323
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Report No.: 50-338/85-34 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Docket No.: 50-338 License No.: NPF-4 Facility Name:
North Anna 1
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Inspection nducted: December 2-5, 1985 Inspector:
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/2!3o!BG J. LI Mathis ~
Date Signed Approved by:
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F. Jape, Section Chief (/
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Date Signed Engineering Branch Division of Reactor Safety SUMMARY
' Scope:
This routine, unannounced inspection entailed 34 inspector-hours on site in the areas of preparation for refueling, refueling activity and spent fuel pool activity.
Results: No violations or deviations were identified.
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8601130316 860 338 PDR ADOCK PDR
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- E. W. Harrell, Station Manager
- J. H. Leberstein, Licensing Coordinator
.A. Neufer, Refueling Coordinator F. P. Miller, Supervisor Quality Control (QC)
J. Smith. Testing Performing Engineer J. A.' Stall, Superintendent, Technical Service Other -licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personnel.
NRC Resident Inspectors M. Branch, Senior Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 5, 1985, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected ~and discussed in detail the inspection findings.
No dissenting comments'were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Unresolved Items Unresolved items were not identified during the inspection.
5.
Preparation for refueling (60705) Unit 1
.During the inspection period, North Anna Unit I was being reloaded for cycle 6.
The inspector verified that the plant was in compliance with selected Technical Specification (TS) requirements for mode 6 during re-fueling.
The inspector verified that testing of equipment used for re-fueling was performed in accordance with adequate procedures, test instrumentation was calibrated, limiting conditions for operation (LCO)
were met, removal' and restoration of affected components were properly
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accomplished,- test results met requirements and were reviewed by p'ersonnel other than ' the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
-Technical Specification 6.8.1.b' requires that written procedures be estab-lished,? implemented and maintained for refueling operations.
During this inspection period, the, inspector reviewed the following Unit I refueling
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procedures:
1-0P-4.2 Reactor vessel head preassemble preparation.
-1-0P-4.3 Reactor head removal 1-0P-4.4 Receipt and storage of new fuel 1-PT-92.1 Manipulator crane operability (hoist)
-1-PT-92.2 Manipulator crane operability (Aux. hoist)
1-PT-96.3-Refueling system circuit test-manipulation crane with dummy fuel assembly ICP-RM-1-RMS-152
'New fuel storage area radiation monitor calibration.
ICP-RM-1-RMS-153-Fuel pit bridge area radiation monitor calibration.
ICP-RM-1-RMS-162, Manipulator crane area radiation monitor calibration.
ICP-RM-1-RMS-163, Reactor containment area radiation monitor calibration.
ICP-RM-1-RMS-164, Incore instrument area radiation monitor calibration.
ICP-RM-1-PMS-165, Containment high range radiation monitor.
Within the a'reas ins'pected, no violations or deviations were identified.
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Refueling Activity (60710)
The cycle 6 reload core was analyzed in accordance with methodology docu-mented in VEPC0 topical VEP-FRD-42, Rev. 1, " Reload Nuclear Design Method-ology". This methodology is consistent with that documented in Westinghouse
.-topical report WCAP-9272, entitled " Westinghouse Reload Safety Evaluation
~ temperature coefficient (MTC) ysis results predict a positive moderator Methodol ogy".. The ! reload anal for beginning of cycle and unrodded core
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A review has been performed by both the station Nuclear Safety and Operating Committee and the Safety Evaluation and control staff.
It has been deter-mined that no unreviewed safety question as defined in 10 CFR 50.59 will exist as a result of cycle 6 reload core.
The inspector witnessed various refueling evolutions during reloading of fuel assemblies from the spent fuel pool to the reactor vessel for Unit 1.
These evolutions included transfer of several fuel assemblies from the spent fuel pool to the transfer cart, verification of the proper fuel assembly by visual observation of identification number, proper operation and control of transfer equipment used during fuel movement and transfer of several fuel assemblies from the transfer cart to the reactor vessel core area in the reactor building.
The inspector interviewed licensee personnel performing the fuel assembly handling evolutions to ensure that personnel were properly trained and were following approved procedures.
The inspector also verified that adequate housekeeping, radiological and accountability controls were established and implemented.
Staffing during reload appeared to meet requirements.
No violations or deviations were identified during this inspection.
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Spent Fuel Pool Activity (86700)
The inspector observed fuel handling operations during reload for Unit 1, cycle 6 in the spent fuel pool area and reviewed procedures related to fuel handling to verify that procedures included the following.
a.
A limitation on the number of fuel assemblies that can be out of safe geometry locations at the same time, b.
Provisions for verifying prior to fuel assembly handling that the spent fuel pool area crane interlock or ph?/sical stops will prevent the crane from passing over fuel storage locations.
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Provisions for verifying prior to fuel h:tndling that the spent fuel pool area ventilation system is operable, d.
Provisions for verifying that minimum water level requirements are monitored during fuel handling operation.
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Provisions for verifying that the spent fuel pool radiation and airborne radioactivity monitors are operable, f.
Provisions for verifying that the spent fuel pool cooling and clean-up system is operable.
No violations or deviations were identified in the areas inspected.