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Safety Insp Rept 50-456/87-03 on 870105-23.No Violations or Deviations Noted.Major Areas Inspected:Action on Previous Insp Findings,Preoperational Test Procedure Verification & Preoperational Test Result Verification
	ML20210S653
Person / Time
Site:	Braidwood
Issue date:	02/06/1987
From:	Azab B, Dupont S, Wright G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20210S617	List: IR 05000456/1987003; ML20210S612;
References
	50-456-87-03, 50-456-87-3, NUDOCS 8702170671
	Download: ML20210S653 (15)
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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-456/87003(DRS)

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Docket No. 50-456 License No. NPF-59 Licensee:

Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:

Braidwood Station, Units 1 and 2 (

laspection At:

Braidwood Site, Braidwood, Illinois

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fm pection Conducted:

January 5-23, 1987 S. G.h'<

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DuPont JL Date <

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B. Az Date Approved By:

rsht / hief 8[0[f7 Test Programs Section Date-Inspection Summary Inspection on January 5-23, 1987 (Report No.-50-456/87003(DRS))

test procedure verification, previous inspection findings, preoperationalpreoperational test r Areas Inspected:

Action on

.preoperational-rest result evaluation.

Results No violations or deviations were identified.

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1.

Persons-Contacted

M. J. Wallace, Project Manager

G. Fitzpatrick, Station Manager

M.E..Lohmann,ProjectStartupSuperintendent

W..E. Hahls, Project Construction Superintendent

C. W. Schroeder, Services Superintendent'

L. Davis, Assistant Superintendent

P. Barnes, Regulatory Assurance Supervisor

S. Stapp,, Quality Assurance

T. J. Lewis, Startup Staff

C. Bedford,in,gulatory' Assurance Re

T.- W.-Simpk Regulatory Assurance

M. Takaki, Regulatory Assurance

Denotes those attending.the exit meeting on January 23, 1987.

2.

' Action on' Previous Inspection Findings (Closed) Open Item (456/86060-02(DRS)):

The recorded test data for preoperational test VP-ll, " Containment Ventilation," did not include the correction factor for densities to the test values.

During the review for acceptance of the preoperational test data, the Project Engineering Department (PED) accepted the test results based upon their calculations-which included the density' corrections but did not document the-calculations in the PED review letter.

Subsequently, PED provided these calculations for review by the NRC. -The PED calcuir 'ons included a

corrected value based upon the design corrected de.d cies (0.075 lbm/ft )

which is extrapolated to the accident density (0.189'lbm/ft3).

PED also concluded that-the ventilation flow' rates will meet the accident requirements. The inspector reviewed the PED calculations and found them

. acceptable. The inspector also verified that the calculations, including F

the density corrections and their bases were included in the completed i

preoperational test result package. The inspector has no further concerns.

preoperational test C5-10, " Containment Spray,y that the method used b (Closed) Open Item (456/86052-03(DRS)): Verif

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to demonstrate that the

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l containment spray nozzles are not obstructed agrees with Table 14.2-18 of l-the FSAR.

The licensee submitted a revision to Table 14.2-18 to Mr. H. R. Denton, Director, Office of Nuclear Regulatory Regulation (NRR)

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on 0ctober 30, 1986. The inspector reviewed the revision tc the FSAR and found that the test method used by preoperational test CS-10 is in L

agreement with the revision.

NRR has also reviewed-the revision and o

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concluded that the next amendment to the FSAR (Amendment 48) will include this revision.

The inspector has no further concerns.

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-(Closed) Open Item (456/86052-02(DRS)):

Acceptance Criteria 4.2 of

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l preoperational test AP-16, " Bus Loading and Independency," requires the

bus to be loaded to greater than or equal to 30% of the startup load; however, the recorded test' data appeared not to meet this criteria.

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Further reviews of the test data by the licensee revealed that the loading requirement of 30% was based upon a varying power factor and loads. The actual recorded value of 7.5 MW instead of 8.5 MW (expected value) was due to an actual power factor of 1.0.

The prescribed test value of 8.5 MW was based-upon a power factor of 0.9.

The licensee re-evaluated the data and concluded that the prescribed value of 8.5 MW was not correct at a power factor of 1.0 and that 7.5 MW was equal to 30% of the startup load. The inspector reviewed these evaluations and found them to be adequate. No further actions by the licensee is required.

(Closed) Open Item (456/86052-04(DRS)): Verify that the results of preoperational test EF-11 "ECCS Full Flow," derronstrated that the Core Spray Pump "1B" was not degraded due to a different Total Developed Head (TDH) while taking a suction from the Refueling Water Storage Tank (RWST)

instead of the containment sump. The licensee reviewed the test data and the purrp curves provided by PED and detennined that the data did not include compensation for the instrument zero drift discovered during the post-test calibration. The licensee corrected the curves to include the instrument zero drift and concluded that the pump was not degraded. The inspector reviewed the corrected curves and agrees that the pump was not degraded. This item is considered to be closed.

(Closed) Open Item (456/86052-05(DRS)): Licensee to complete actions required by Construction Work Request (CWR) NR-10-09. The CWR was initiated to resolve a preoperational test deficiency (NR-10-175)

where the Upper and Lower Deviation channels could not be tested during preoperational test BWPT-NR-10 " Neutron Monitoring - Excores."

Westinghouse was requested, by the licensee, to provide a guideline for testing the Upper and Lower Deviation channels. The Westinghouse provided guidelines were incorporated in the station procedure BWIP 2505-001, " Calibration of Nuclear Instrumentation System Flux Deviation NSO INY-NR8050" which was perfomed on August 13, 1986. The inspector verified that BWIP 2504-001 met the objectives of section 9.20 of the preoperational test BWPT-NR-10. This item is considered to be closed.

(Closed) Open Item J456/86027-01(DRS)): The licensee should evaluate the measuring and test equipment (M&TE)_ calibration and tracking programs of the Instrument Maintenance and Electrical Maintenance Departraents to resolve differences in the program that could possibly result in the failure to trace an out of calibration instrument to the applicable preoperational test. The inspector discussed with the licensee their l

evaluation and conclusion as follows: The Electrical Maintenance Department tracks N&TE usage and calibration results on an individual bases while the Instrument Maintenance Department issues calibration results for all instrurrents at the same time.

In addition, all instruments used during preoperational testing are listed in the applicable preoperational test procedure. The licensee concluded that the method used by the Electrical Maintenance of providing individual notification of out of calibration M&TE will be used by all station departments. The inspector found this to be acceptable.

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3.

Preoperatic_nal Test Procedures Verification The' inspector reviewed the following preoperational test procedures and verified that they were written, reviewed, and approved by the licensee in accordance with the requirements of Regulatory Guide 1.68 and the licensee's Quality Assurance Manual:

.BWPT-FH-10, Revision 1 " Fuel Handling Tools"'

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BWPT-FH-11, Retest 65, " Fuel Handling Transfer System" BWPT-GW-10, Revision 1, " Radioactive Gas Waste" BWPT-RC-12, Revision 0, " Reactor Coolant" BWPT-VQ-10, Revision 2, " Containment Purge System" PWPT-DC-50, Revision 1, "125 V DC Distribution"

'No violations or deviations were identified.

4.

Preoperational Test Resu_lts Verification The inspectors reviewed the following preoperational test procedure and verified that the results were reviewed against approved acceptance criteria and an evaluation of the test results had been performed in accordance with Regulatory Guide 1.68 and the licensee's Startup Manual:

BWPT-FH-10, Revision 1, " Fuel Handling Tools" BWPT-FH-11, Retest 65, " Fuel Handling Transfer System" BWPT-GW-10, Revision 1, " Radioactive Gas Waste System" BWPT-IT-10, Revision 0, "RTD Cross Calibration-Safety Related" BWPT-RC-12, Revision 0, " Reactor Coolant System" BWPT-RC-12, Retest 102, " Reactor Coolant Wide Range Pressure Loops and CV Miniflow Valves" BWPT-VQ-10, Revision 2, " Containment Purge"

'BWPT-DC-50, Revision 1, "125 V DC Distribution" BWPT-RY-10, Revision 0, and Retest 79, " Pressurizer" BWPT-VA-11, Revision 2, " Containment Ventilation"-

BWPT-RY-17, Revision 1, " Pressurizer (IHF)"

BWPT-VA-10, Revision 1, and Retests 107 and 131, " Auxiliary Building Ventilation Cubicle Coolers" No violations or deviations were identified.

5.

Preoperational Test Result Evaluation The inspector reviewed the results of the following preoperational tests to verify that all test changes were identified'and approved in accordance with administrative procedures; all test deficiencies were appropriately resolved, reviewed by management and retested as required; test results were evaluated by appropriate engineering personnel and specifically compared with acceptance criteria; data was properly recorded, signed, dated, and documented; test packages were reviewed for adequacy of contents; and test results were approved by appropriate personnel:

BWPT-SI-12, Revision 0, Retest 90, " Safety Injection" BWPT-EF-12, Revision 3 " Engineer Safety Features" BWPT-AF-10, Revision 2. " Auxiliary Feedwater"

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Pertaining to BWPT-AF-10, three retests (R-75; R-105 and R-140) were-not available for review. This is considered to be an Open Item-(456/87003-01(DRS)) until the NRC can review the test results and ascertain that all of the BWPT-AF-10 testing requirements have been met.

6.

Open Item 0)en items are matters which have been discussed with the licensee, w1ich will be reviewed further by the inspector, and which invclves some action on the part of the NRC or licensee or both.

An Open Item disclosed during this inspection is discussed in Paragraph 5.

7.

Exit Interview The inspectors met with licensee re)resentatives (denoted under Paragraph 1) at the conclusion of tie inspection on January 23, 1987.

The inspector summarized the purpose and findings of the inspection.

The licensee acknowledged this information.

The licensee did not identify any documents / processes as proprietary.

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D 051*3 SALP FUNCTIONAL AREA A55E55ENT AND PRELIMINARY INSPECTOR EVALUATION FORN

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M,beo) d Inspection Report No.: 1C7o03

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Management Involvement in Assuring Quality.

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Approach to Resolution of Technical Issues from a Safety Standpoint.

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Responsiveness to NRC Initiatives.

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Enforcement Nistory.

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Operational and Construction Events.

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Staffing (including management).

RATING KEY: (For Categories 2 - Declining and 3, provide narrative basis for conclusion)

Category 1 Category 2 - Declining Category 2 Category 3 Inspector (s) concerns adequately addressed or

l-l Inspection Evaluation Form being processed.

LeadInspect[or15dd, f/s-d7 lL N/[7

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