ML20246D448

Forwards Plant Status Rept for 890719-0816

ML20246D448
Person / Time
Site:	Peach Bottom
Issue date:	08/18/1989
From:	Doerflein L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Kane W NRC
References
NUDOCS 8908280096
Download: ML20246D448 (4)

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18 AUG 1989 MEMORANDUM F0P: , William F. Kane, Director, Division of Reactor Projects FROM: Lawrence T. Doerflein, Chief, Reactor Projects Section 2B St;BJECT:

PEACH BOTTOM '.TOMIC POWER STATION STATUS REPORT FOR THE PERIOD FROM vuLY 19 TO AUGUST 16, 1989 Enclosed is the Peach Bottom periodic status report from the NRC Restart staff at the Resident Office at Peach Bottom. The NRC restart staff inspectors monitored activities at the plant during the report period.

These status reports are intended to provide NRC management and the public with an overview of plant activities and NRC insnection activities.

Subsequent inspection reports will address many of these topics in more detail.

OMmtn gcgg gy Lawrence T. Doerflein, Chief, Reactor Projects Section 2B i

Enclosure:

As Stated l I l

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D 1 0FFICIAL RECORD COPY PB STATUS REPORT 7/19-/8/16 -

0001.0.0 08/17/89 /

8908280096 890S18 , ,9 1

PDR ADOCK 05000277

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William F. Kane. 2 cc w/ enc 1:

C. A. McNeill, Executive'Vice President-Nuclear Dickinson M. ' Smith, Vice President, Peach Bottom Atomic Power Station J. F. Franz, Plant Manager D. Helwig, General Manager,_ Nuclear Services E. C. Kistner, Chairman, Nuclear Review Board Troy B. Conner, Jr., Esquire Jack Urban,- General Manager, Fuels Department, Delmarva Power

.W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric B. W. Gorman, Manager - External ~ Affairs, PSE&G Eugene J. Bradley, Esquire, Assistant General Counsel Raymond L. Hovis, Esquire

. Thomas Magette, Power Plant Siting, Nuclear Evaluations W. M. Alden, Director, Licensing Section Doris Poulsen, Secretary of Harford County Council Dane Honan Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety' Info mation Center (NSIC)

NRC Resident Inspec;or Commonwealth of Pennsylvania bec w/ enc 1:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o enc 1)

L. T. Doerflein, Section Chief, DRP PA0 (2) SALP Reports Only + All Inspection Reports Robert J. Bores, DRSS W; Pasciak, Chief, FRPS, DRSS '

SRI, Limerick I Karl Abraham, 9ublic Affairs Officer (2)

R. E. Martin, Project Engineer, NRR l

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R(I:DRP Rl DRP j[J6hnson / Doerflein Linville 8/O/89 8/lS/89 84 /89 0FFICIAL RECORD CDPY PB STATUS REPORT 7/19-/8/16 - 3 0002.0.0 1 08/17/89 )

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I ENCLOSURE PEACH BOTTOM ATOMIC p0WER STATION STATUS REPORT FOR THE PERIOD j

July 19 - August 16, 1989 i J

1.0 Plant Status  !

As of 8:00 a,m. on August 26, 1989, the Unit 2 reactor is in the RUN y mode at 100% power. Unit 2 is at the steady state power level for the >

100% NRC holdpoint. Unit 3 is in the refueling mode with the core off loaded into the spent fuel pool.

2.0 Facility Operations Summary 2.1 Unit 2 Around-the-clock NRC shift coverage was recommenced on July 21, 1989, in preparation for power ascension from 70% to 100%. The unit automatically scrammed f rom 79% power on July 21, 1989, during troubleshooting of the electro-hydraulic control system. The unit was restarted on July 27, 1989. On August 4, 1989, Unit 2 achieved 100% power and around-the-clock NRC shift coverage was suspended in accordance with the NRC restart inspection plan. On August 13, 1989, the licensee reduced power to 30% to repair a turbine control valve scram pressure switch. The unit was returned to full power on August 15, 1989.

2.2 Unit 3 Unit 3 ccntinues in its seventh refueling outage that began October 1, 1987. Unit 3 outage work including maintenance and modification activities is in progress. Returning systems to support core r-load is the major activity on Unit 3.

3.0 Items of Specici Interest 3.1 On July 21, 1989, the NRC granted approval to PEco to increase Unit 2 power to 100%.

3.2 Unit 2 automatically scrammed from 79% power on July 21, 1989, due to a raain steam isolation valve closure during troubleshooting of a drifting reactor pr essure regulator in the electro-hydraulic control system. The plant responded normally and operators used safety systems per emergency operating procedures. The unit remained in hot shutdown to perforra maintenance and subsequently restarted July 27, 1989.

3.3 The licensee made six emergency notification system (ENS) calls during the period. Two calls were made on July 22. 1989, concerning l the Unit 2 scram that cccurred on July 21, 1989. Two ENS calls were O

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made,on July 20, 1989, concerning an inoperable transversing in core-probe' containment isolation vaive and initiation of a shutdown required by technical specification limiting condition for operation. This required the licensee to place the onit in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The licensee closed the containment 1 solation valve and the shytdown was stopped.

Another ENS call was made on August 9, 1989,.due.to an unplanned'

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lifting of a safety. relief valve during testing. On' August 10, 1989, the licensee made two ENS calls to report that a' timer in the 0 automati:: depressurization system was inoperable Th9s required the

' initiation of a shutdown; however, repairs were made and the~ shutdown was' stopped. Another ENS call was made on August 11, 1989, to report inoperability of the high pressure coolant injection system.

These ENS calls and related events will be the subject of future inspection reports.

4.0 NRC Activities During the period 4.1 The NRC restart staff continued to monitor licensee's activities.

Around-the-clock shift coverage was in place between July 21, 1989 and August 4, 1989. Expanded resident coverage was in place during the remainder of the period. Thise. individuals consisted of the following:

Thomas P. Johnson - Senior' Resident Inspector.

Richard J. Urban - Resident Inspector Larry E. Myers - Resident Inspector Mark Riches - Licensing Engineer Carl Sisco - Licensing Engineer Jack Gadzala - Resident Inspector Larry.Scholl - Resident Inspector Lynn Kolonauski - Reactor Engineer Areas inspected included the power ascension testing program, operational safety, training activities, radiation protection, physical security, control. room activities and demeanor, reportable events, surveillance testing, outage activities, maintenance, and outstanding items. These itens wfil be the subject of a future inspection report.

4.2 NRC management personnel were on site as follows:

Ronald Bellamy, Chief, Facilities Radiological Safety and Safeguards Branch, DRSS on July 27, 1989.

Edward Greenman, Director, Division of Reactor Projects, Region III on August 15, 1989.

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