IR 05000412/1987059
| ML20236A142 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/08/1987 |
| From: | Eapen P, Wen P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236A137 | List: |
| References | |
| 50-412-87-59, NUDOCS 8710220064 | |
| Download: ML20236A142 (4) | |
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U.S. NUCLEAR REGUUJORY: COMMISS7.ON REGION Iu e
Report No~.
50-412/87-59 Docket'No.
50-412 License No.
Licensee:
Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania-15077
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Facility Name:
' Beaver Valley Unit'No. 2
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Inspection At:
-Shippingport, Pennsylvania'
Inspection Conducted:
LSeptember 8-11, 1987 Inspector:
d I. b
/0/8/87 P.-C. Wen, Reactor Engineer, Special Test
,cate<
Pr grams Sec on EB, DRS M
/d 87.
j Approved f~-67
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v r Dr. P. K. Eapen,~ Chid (/ Special Test
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Programs Section,'EB, DRS-l l
Inspection Summary:
Inspection on September 8-11, 1987 (Inspection Report No. 50-412/87-59)
l Areas Inspected: Startup Test Program review and Power. Ascension Test Witnessing.
Results: No violations were identified.
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DETAILS.
1.0' Persons Contacted Duquesne Light Company
- J. Godleski, TCT Engineer
- D. Hunkele, Director, QA Operations
- J. Johns, Supervisor, QA Surveillance T. F. McGourty, Principle Engineer
- T. P. Noonan, Assistant Plant Manager
- R. G. Williams, Principle Engineer
- G. Zosack, Compliance engineer j
T. G. Zyra, Director, Site Test and Plant Performance l
U.S. Nuclear Regulatory Commission
- J. Beali, Senior Resident Inspector L. Prividy, Resident Inspector The inspector also contacted other administrative and technical licensee personnel during the course of the inspection.
- Denotes those present at the exit meeting held on September 11, 1987.
2.0 Power Ascension Testing
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2.1 Startup Test Program i
The licensee performed two major transient tests (Main Steam l
Isolation Valve Closure Test and Loss of Power Test) during this
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inspection period (September 8-11, 1987). After completing
startup testing through 50% power plateau, the un.it was shut down on September 11, 1987 for a planned mini maintenance outage, i
The Load Rejection Test (IST-2.04.06) at 50% power level was deleted.
Instead, a 10% load swing test was performed at'50% power.
This test change was approved by the Joint Test Group (JTG) and Onsite Safety Committee (OSC). Additionally, load rejection test at 50%
power level is not one of the regulatory positions in Regulatory Guide 1.68.
The inspector had no questions.
2.2 Test Witnessing
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The inspector witnessed entire portions of the tests described below.
These tests were observed against the attributes identified in Inspection Report 50-412/87-55, section 2.2.
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f Main Steam Isolation Valve (MSIV) Closure Test (IST-2.21A.02)
This test was performed on September 9, 1987 at 30%' power level by)
simultaneous 1y' closing all.3 MSIVs.. -Upon MSIVs closure,- the: steam-generator levels shrunk from. normal (~41%) to' low-low. level, and
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caused reactor trip. The actions'of the control room operators-following the reactor trip.were:in accordance'with established:
procedures.
The MSIVs.were. reopen to restore the normal path of'
decay heat removal; the unit was' stabilized shortly'in.accordance with plant. procedure.
Preliminary test.results indicated that;all MSIV closure times met the test acceptance criteria-(5 seconds /from
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the time the valve received the signal to the time:the valve' fully closed). However,:the feedwater' flow and_the associated steam.
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generator level control did not respond. adequately.
The licensee and
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reactor vendor were evaluating' the: test results.
The inspector:wil1<
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l-follow this in a future inspection.
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l Loss of Power Test (IST-2.04.03)
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On September 9, 1987 with the reactor at approximately 30%, the.
i licensee performed a loss of. power test.in accordance with test-procedure IST-2.04.03, " Verification of Plant Performance.Following a Turbine Trip Coincident with'a Los of Offsite Power ~at Load." 'The l
inspector observed the test briefing between the test. engineers and-
operations personnel' prior to the conduct.of the test.
The' test-
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briefing was thorough and comprehensive..The' inspector 'also verified '
that the required prerequisites'had been completed.
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Prior to the test, auxiliary electrical load was being supplied by Unit Station Service Transformers TR-2C and TR-20.
The-test'was initiated by manually tripping the turbine generator. 'The emergency diesel generators, loading sequence, and plant system's responded as designed. As part of the test, electric power to the 'RCPs'was -
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removed and the plant went into-natural circulation.
During t_his
test the performance of the Turbine-Driven Auxiliary Feedwater Pump
was also verified.
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Preliminary results indicated that the plant responded as designed following the turbine trip with no offsite power. However, such l
equipment problems as the malfunction of the plant paging. system were
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identified. The licensee is currently evaluating test results.. The.
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inspector will follow this in a future ' inspection.
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i Summary The licensee conducted these transient tests in accordance with approved test procedures by highly qualified test personnel. These tests met the test objectives.
No unacceptable conditions were identified.'
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3.0 Independent Verification
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During the loss of power test, the inspector independently verified the l
plant response.
For' example, the inspector assured that the reactor-
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entered natural circulation by observing that (1) there was ~approximately.
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19 F - ' difference between T and T temperatures (2) T and incore hot cold hot q
thermocouple temperatures were tracking closely and (3) there was i
sufficient subcooling within the reactor.
4.0 QA/QC Interface j
i The licensee QA Surveillance Group continuously provided test coverage
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for the startup test program. During this ' inspection-period, the
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I inspector noted that QA personnel were actively following startup pro--
gram tests. Appropriate surveillance ' reports WEre issued.
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No unacceptable conditions were identified.
l 5.0 Exit Meeting
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An exit meeting was held on September 11, 1987 to discuss the inspection scope and findings, as detailed in this report (see paragraph 1.0 for attendees).
l At no time during this inspection was written material provided to the i
licensee.
Based on the NRC Region I review of this report and discus-
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sions held with the licensee representatives'at the exit, it was I
determined that this report does not contain information subject to 10 CFR 2.790 restrictions.
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