ML20006C558

Unit 1 Startup Test Rept (Suppl 14). W/900131 Ltr

ML20006C558
Person / Time
Site:	River Bend
Issue date:	01/27/1990
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-32234, NUDOCS 9002080226
Download: ML20006C558 (7)

Text

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GL/LF STATES . UTELITIES COMPANY n,e mau.w. .w n, . a e m m n i.msa a u, .ee,m ADIA(G51I>N OW WM 346 fWi1 January 31,1990 RBG-32234 File Nos. G9.5, G9.25.1.5 U. S. Nuclear Regulatory Commission Document Control Desk WLshington, D.C. 20555 Gentlemen:

River Bend Station - Unit 1 Docket No. 50-458 Enclosed is Supplement 14 to the.Startup Test Report for River Bend Station - Unit 1. This report covers the period through January 27, 1989. This information is provided pursuant to Technical Specifications 6.9.1.2 and 6.9.1.3 and Regulatory Guides 1.16 and 1.68. An additional report will follow within three months pursuant to Technical Specification 6.9.1.3.

Sincerely, J..F.Aix/p J E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/ SF/ch ONL/p%

Enclosure

.cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 St. Francisv111e, LA 70775 Mr. Walt A. Paulson Project Manager, River Bend Station Document Control Desk Washington. 0.C. 20555 h 1 90020e0226 900127 #

gDR ..ADOCK 05000458 PDC (l

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GULF STATES UTILITIES COMPANY i RIVER BEND STATION-UNIT 1 >

i STARTUPTESTREPORT(SUPPLEMENT 14) l t

t 27 JANUARY 1990 r

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STARTUP. TEST REPORT (SUPPLEMENT 14) i

1. The River Bend - Unit 1 Startup Test Program was concluded on June 16, 1986. This supplemental report provides the current status of open test exceptions from the October 27, 1989 supplement of the Gulf States Utilities Company, River Bend Station - Unit 1. Startup Test Report. Since the October 27, 1989 report, six test exceptions heve been closed and three open test exceptions remain.

2. All open test exceptions are categorized as affecting level 2 i criteria or lower. Any level I criteria failures referenced  ;

in previous supplements were downgraded to level 2 criteria .

as a result of appropriate engineering analysis and are  ;

considered level 2 criteria in this report. This is j consistent with the treatment of all test criteria referenced d in the initial Startup Test Report. All open test exceptions were evaluated and approved by the on-site review committee for continued, safe, full power operation of River Bend Station - Unit 1.

3. Currently, the test exceptions are assigned to the individual system engineers to which the exceptions are most applicable.

It is believed that each engineer's knowledge of the system will aid in expediting the closure of the test exceptions.

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- ST-13 Process Computer r

TE-12: Status: Closed Temperature calibration problems were discovered as a result of balance of plant testing. These problems are still in the process of being corrected. This test exception involves balance of plant performance calculations and has no impact on any safety-related portion of the plant. Correction of the problem is still being pursued. However the calculations by the plant process computer are merely a convenience, not a necessity. At this time the calculations are being done en a personal _ computer with the data entered manually. This level 2 exception was evaluated as not impacting safe, full power operation. This test excoption has been reviewed by the Facility Review Committee (FRC) and recommended for closure.

ST-22 Pressure Regulator TE-22: Status: Open The main turbine pressure regulator failed the level 2 criteria for incremental regulation. Operation of the system through actual plant transients, including recirculation system flow control valve runbacks, single loop operation, power changes at various rates and numerous startups and shutdowns since initial criticality, has demonstrated that this system performs satisfactorily. Engineering is evaluating data collected during plant power maneuvers to evaluate the closure of this test exception. This exception has been determined not to impact safe, full power operation.

ST-23A Water Level Setpoint, Manual Feedwater Flow Changes TE-19: Status: Closed Based on the operating history of the feedwater system through normal operating transients, it has been determined that retesting is not necessary and that the feedwater level control system has been proven to be reliable and responsive. Although testing of individual valves was not possible, sufficient data exists to show that the system does respond in a linear fashion.

This exception dealt with system reliability and did not concern plant safety. This level 2 exception was evaluated as not impacting safe, full power ope' ration. The FRC has reviewed this test exception and recommended it for closure.

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ST-25C/D Main Steam Line riow Instroentation TE-3: Status: Open The elbow tap flow versus delta P curves are not within + 5% of the design curves. Elbow tap flow data were taken during power '

ascension following the first refueling outage. Engineering is evaluating field data to determine required main steam line flow instrumentation calibration changes. General Electric (GE) has evaluated this data and has agreed with GSU that this level 2  ;

test exception does not impact safe, full power operation. '

ST-30C Recirculation System Performance 1

TE-3: Status: Open The recirculation system flow control valve mismatch that existed was reduced from 14% to 7% and the core and drive flow shortfalls have been resolved. Evaluation is continuing to resolve the below design acceptance of the M ratio for the loop b problem.

Retest may be required to adequately disposition the M ratio problem due to the reduced flow control valve mismatch. A retest procedure has been drafted by on-site GE personnel. Evaluation of data obtained during plant power maneuvers continues. This .

level 2 test exception does not impact safe, full power operation.

ST-95 Emergency Response Infomation System TE-3: Status: Closed ,

Module S0-10 of the emergency response information system (ERIS) which performs scram timing, failed. This module addressed the set am time of only one rod. Work requests for correcting the problem were completed. However, this module failed again during retest. Plant maintenance and engineering personnel are ,

evaluating the cause of the second failure. This test exception is being closed because the rod's scram time is obtainable by attaching a strip-chart recorder to a permanent GE panel in the main control room. Scram times are then calculated manually.

The FRC has concurred with this evaluation. This level 2 exception does not impact safe, full power operation. .

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ST-100 Piping Vibration i

TE-16: Status: Closed Vibration data for MSS Points T42 and T220 was not available due

• to the failure of the ERIS data collection panel 113. Both of these points are located on non-safety related main steam piping. .

Data were obtained for one of these points during transients, I which were more severe than those called for in the test. The

, data were found acceptable. No data were available for the second point. However, the plant has experienced the most severe

s. transient postulated for these pipes several times. A- detailed inspection of this piping and its associated supports during the last refueling outage revealed no abnormalities. Therefore, this piping is considered acceptable. This level 2 test exception does not impact safe, full power operation. This Test Exception has been evaluated by the FRC as accept-as-is based on a review of available data, operating history, and field inspection.

TE-20: Status: Closed ,

During generator load rejection (ST-27) points, MSS T-42Z, T235X, Y & Z, and FWS T-144X failed Level I criteria. MSS T-42X and FWS T-144& and Z failed level 2 criteria. No data was available for condensate test point T/S-525 since CNN-A0V 119 failed to open.

The data that exceeded the level 1 and 2 criteria were evaluated l prior to the closure of the start-up test program and determined to be acceptable. The remaining portion of the exception (T/S-525) involves only a portion of non-safety related condensate piping. This piping has been subjected to several load rejections during and since initial plant start-up. A detailed inspection of this piping and its associated supports '

during the last refueling outage revealed no abnormalities.

Therefore, this piping is considered acceptable. This Test Exception has been evaluated by the FRC as accept-as-is based on a review of available data, plant operating history and field inspection, i

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TE-21: Status: Closed Test points MSS- T-200, FWS T-39, SVV T-39 and T-85 were not operable during generator load rejection. Point MSS T-200 is on '

i nonsafety-related piping, points FWS T-39, SVV T-39 and SVV T-85 are on safety related piping. Point MSS T-200 is considered '

acceptable based on detailed field inspection of the piping and supports, and on comparison with other MSS points. Point FWS ,

T-39 is acceptable based on ASME XI Inservice Inspections of '

piping and supports..and on comparison with other FWS points.

Points SVV T-39 and SVV T-85 are acceptable based on ASME XI ISI  ;

Inspections and on comparison with data. for these points' from ,

other transients. The only significant transient these points i experience is the lifting of a main steam safety relief valve  ;

(the points are on an SRV tailpipe). Data for relief valve -l

. actuation were collected during other tests and were found to be satisfactory. This Test Exception has been evaluated by the FRC l as accept-as-is based on a review of available data, plant l

operating history, and field inspections. j i

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