ML20195H593

Forwards Sixth Status Rept Identifying Changes to Initial Test Program as Described in Chapter 14 of FSAR

ML20195H593
Person / Time
Site:	Beaver Valley
Issue date:	01/07/1988
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-8-001, 2NRC-8-1, TAC-63534, NUDOCS 8801200267
Download: ML20195H593 (3)

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• January 7, 1988 Shipptr.gort. PA 15077-0004 2NRC-8-001 United Stated Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 ,

BVPS-2 FSAR Chapter 14, Test Change Status Report Gentlemen:

Forwarded to NRC is the sixth status report identifying changes to the Initial Test Program as described in Chapter 14, of the FSAR.

are made in accordance with the provisions of These changes 10CFR50.59 and reported to NRC in accordance with 50.59(b) within one month of initiating changes per BVPS-2 Facility Operating License condition C.(3).

Ve y t u y yours, i db

. . Carey Senior Vice President Nuc1 car Group Attachment cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Project Manager Mr. P. Wen NRC Reactor Engineer, Region I INPO Records Center 8801200267 880107 PDR ADDCK 05000412 R PDR 11 4 'b

y BVPS-2 FSAR Chapter 14 Test Change Status Report FSAR SECTION TITLE

1. 14.2.12.57.01 Plant Communications Test (SOV)

(SOV-2.40A.01)

Test SOV-2.40A.01 was scheduled to be completed by December 31, 1987. Communications required by Technical Specification 3.9.5 to support refueling were tested satisfactorily and used during the Initial Core Loading. Approximately 70% of this test has been performed. Modifications are presently being made to this system, and it is anticipated that the remainder of this test will be completed by the First Refueling.

2. 14.2.37. 73.02 Non-QA Category I Heat Tracing (SOV-;.45D.01) System Test (SOV)

Test SOV-2.45D.01 was scheduled to be completed prior to December 15, 1987. The systems involved are operable however, only approximately 80% of the circuits are successfully tested. Final testing is scheduled to be completed by the First Refueling.

There are no Technical Specification requirements associated with these systems.

3. 14.2.12.77.01 Fuel Handling Test (PO)

(PO-2.66.01)

Reference:

(a) DLC Letter 2NRC-7-143 dated May 25, 1987, "Plant Readiness for Fuel Loading" Based on the present licensing commitment, PO-2.66.01, "Fuel Handling Equipment Test" was required to be completed prior to core load. During preparation of the BVPS-2 Startup Report on December 16, 7.987, it was discovered that this test was not included in Reference (a) as a deferred test. Our intentions to defer rotesting until prior to the First Refueling were fully visible in the Test Results Report as approved by the Joint Test Group and the Onsite Safety Committee, and in the Testing Tracking Computer Printouts.

Sequence of Events that affect this test deferral are as follows:

a) On May 23, 1987, the subject test was satisfactorily completed and evaluated against the acceptance criteria to support fuel load. Test deficiencies were also evaluated and determined not to have any impact on core load. Steps deferred due to equipment unavailable for testing, were identified in the preliminary draft TRR which stated they would be deferred until after core load.

1-

BVPS-2 FSAR Chapter 14 Tost Chrnga Stetum Report, (Cont'd)

FSAR SECTION T_ITLE 14.2.12.77.01 Fuel Handling Test (PO), Cont'd (PO-2.66.01) b) On June 5, 1987, Retests66-002, 3, 4, 5 and 6 were generated to track untested steps. Deferral of these steps was not formally submitted to the NRC, but the Systems Testing Section's intentions to defer the steps was fully visible in the approved TRR and in In-house Testing Tracking Computer Printouts made available to the NRC. The TRR was approved on August 28, 1987 and the Computer Printouts were updated on an ongoing basis fully stating that these retests were not required to be completed until prior to the first refueling.

The retests were also discussed as deferred in IST-2.01A.10, "Startup Testing Program". The failure to properly document this test deferral was attributed to an oversight in the test deferral process.

c) On December 16, 1987, while preparing the BVPS-2 Startup Report, a Test Engineer discovered that Retests66-002, 3, 4, S and 6 were not deferred until after core load, and prior to the first refueling as previously thought. Retests66-002, 3, 4 and 6 were completed on September 4, 1987, however, Retest 66-005 still remains to be performed. Due to Licensing notification requirements, the NRC was notified on the red phone in the Control Room within the twenty-four (24) hour requirement. Personnel involved have been cautioned on properly documenting startup testing deferral requirements.

There were no safety implications to the plant or public as a result o# this event. The components listed in this test deferral are not required to support normal plant operation.

Unit 2 has been operating at normal power operation and is not affected operationally by this test deferral.

This report is being submitted in accordance with the License requirements and the requirements specified in 10 CFR 50.73.

This test satisfactorily completed all testing required to support fuel load. There are no Technical Specification requirements for the Fuel Handling Equipment affected and the untested equipment is not safety related. The untested equipment was not needed during initial core loading and is not required to be available until the First Refueling. All retesting was completed prior to Commercial Operations except for testing of the RCC Change Fixture (Retest 66-005) which is being deferred until the First Refueling.