ML20235Y035

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Forwards NRC Resident Ofc Biweekly Status Rept for 870703- 0716
ML20235Y035
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/21/1987
From: Linville J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Kane W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8707250038
Download: ML20235Y035 (5)


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21 JUL 1987 I

l Docket Nos. 50-277 i 50-278 l MEMORANDUM FOR: William F. Kane, Director, Division of Reactor Projects i FROM: J. C. Linville, Chief, Reactor Projects Section 2A ]

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SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION STATUS REPORT FOR THE PERIOD JULY 3 - JULY 16,1987 l

l Enclosed is the Peach Bottom periodic bi-weekly status report from the NRC l Resident Office at Peach Bottom. Three NRC resident inspectors and region-I based specialist inspectors monitored activities at the plant during the I report period.

l These status reports are intended to provide NRC management and the public with  ;

an overview of plant activities and NRC inspection activities. Subsequent l inspection reports will address many of these topics in more detail. )

i nr i=1 Signed by:

James C. Linville, Chief Reactor Projects Section 2A l

Enclosure:

As stated l

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l l 8707250038 870721 l PDR ADOCK 05000277 R PDR 0FFICIAL RECORD COPY 616 LINVILLE 7/17/87 - 0001.0.0 07/20/87

21 JUL 1987 l

cc w/ enc 1:

Dickinson M. Smith, Manager, Peach Bottom Atomic Power Station John S. Kemper, Senior Vice President, Engineering and Production Thomas S. Shaw, Jr., Vice President, Production Troy B. Conner, Jr. , Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric G. Leitch, Nuclear Generation Manager j Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)

Raymond L. Hovis, Esquire Thomas Magette, Power Plant Siting, Nuclear Evaluations 4

W. M. Alden, Engineer in Charge, Licensing Section i Doris Poulsen, Secretary of Harford County Council l Public Document Room (PDR) J' Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Pennsylvania I

i bec w/encls: d l

Region I Docket Room (with concurrences)

J. Taylor, EDO T. Murley, NRR R. Starostecki, NRR F. Miraglia, NRR S. Varga, NRR

8. Boyer, NRR ,

W. Butler, NRR )

R. Martin, NRR 1 i W.. Russell, RI W. Johnston, RI T. Martin, RI S. Collins, RI R. Gallo, RI l K. Abraham, RI M. Miller RI l l

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RI:DRP R.. RP :DRP  ;

Scholl/rh1 L'nville allo 189 7ho/87 7/7#/87 7/p/87 0FFICIAL RECORD COPY 616 LINVILLE 7/17/87 - 0002.0.0 07/20/87

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ENCLOSURE j 1

PEACH BOTTOM ATOMIC POWER STATION STATUS REPORT FOR THE PERIOD JULY 3 - July 16,1987 l

1.0 Plant Status I As of 8:00 a.m., on July 16,1987, Unit 2 is in a refueling outage with l all of the fuel reloaded into the reactor core. Unit is being prepared  !

for reactor pressure vessel reassembly. Unit 3 is ir cold shutdown per i the March 31, 1987, NRC Order with coolant temperature at approximately i 140 degrees Fahrenheit. l 2.0 Facility Operations Summary l

Unit 2 has been in a refueling outage since March 13, 1987. Unit 3 has been in a cold shutdown condition per the March 31, 1987, NRC Order since ,

April 1,1987. I 3.0 Items of Special Interest Control Room Staffig l On July 6 one half of the control room operators commenced an operator I training course which is intended to be part of the recovery plan.

Licensing of GE Engineers On July 13 a meeting was held at the NRC Region I office to discuss the possible licensing of GE engineers to supplement the PECO operating staff on an interim basis during the restart effort. The licensee and GE management presented this plan to NRC Region I staff.

Licensee Briefing of NRC Management l

A meeting was held on July 15, 1987 at the NRC Headquarters in Bethesda, Maryland during which licensee management briefed the NRC management on '

the status of their restart recovery plan.

4.0 Other Items of Interest The licensee reported that incorrect piping configurations existed in the control room ventilation radiation monitoring (CRVRM) system. As a result, the CRVRM system would not have been able to detect radiation conditions as designed. The cause of the incorrect piping alignment is 0FFICIAL RECORD COPY 616 LINVILLE 7/17/87 - 0002.1.0 07/17/87 4

unknown; however, the licensee believes that this condition has existed since initial plant startup in 1973. The CRVRM system provides for emergency filter actuation and control room isolation under a high radiation condition. As a result the control room habitability during ,

accident conditions would not have been assured. The licensee has  !

corrected the discrepancies in the CRVRM system, and checked other ventilation radiation systems, with no additional errors found.

At 1:09 p.m. on July 8, 1987, a contractor employee was found to be l carrying an apparent controlled substance in a cigarette pack while -

entering the protected area. During a routine loose-object search, a L security guard noticed a piece of tape covering the opening of the employee's cigarette pack, in which a small bag of white powder was discovered. He stated that the substance was methamphetamine and he has never brought in or used drugs in the protected area. However, he did admit to storing drugs in his car on licensee property. His employment was terminated by the contractor, his security badge was pulled and he was escorted off site. The Nuclear Emplojee Data System (NEDS) was notified. The resident inspectors were notified by the licensee at 2:45 p.m.

At 9:05 a.m. on July 10, 1987, the Unit 2 shutdown cooling system isolated due to a blown fuse. A loss of power to the system logic caused shut-down cooling containment isolation vahes to close and the 2A residual heat removal pump to trip. The cause of the blown fuse is under  ;

investigation. The licensee replaced the fuse, reset the isolations, I restored shutdown cooling and notified the MC at 10:50 a.m. Unit 2 was i in the refueling mode with coolant temperature about 105 degrees F.

At 3:28 p.m. on July 10, 1987, a lightning strike during a storm caused a partial loss of off site oower. A breaker tripped resulting in a loss of the #3 startup source for both units. This resulted in a loss of the associated 13 KV nor vital auxiliary buses and a fast transfer of the 1

associated 4KV emergency buses to the #2 startup emergency source. The fast transfers actuated as designed and no diesel generator starts occurrred. Group II and III containment isolations occurred on both units, including a loss of shutdown cooling. The licensee transferred loads to the #2 startup source per procedure and restored shutdown cooling. The licensee ratified the NRC Headquarters at 5:15 p.m.

The resident inspectors are following the investigation and resolution of these items.

5.0 NRC Activities During the Period Three NRC Resident Inspectors monitored plant activities between Juiy 3 and July 16, 1987. These individuals consisted of the following:

Thomas P. Johnson - Senior Resident Inspector Richard J. Urban - Resident Inspector Larry E. Myers - Resident Inspector - Attending training at NRC Training Center in Chattanooga July 13-24 0FFICIAL RECORD COPY 616 LINVILLE 7/17/87 - 0003.0.0 07/21/87

Other Region I personnel on site during th's period included the following individual:

Thomas F. Dragoun - Radiation Protection Inspector, Region I The monthly resident inspection report period ends on July 17, 1987 (50-277/87-17; 50-278/87-17). The report covers the period from June 1 to July 17, 1987. Areas inspected included operational safety, shutdown Order ,

commitments, radiation protection, physical security, control room activities I and demeanor, reportable events, surveillance testing, refueling and outage I activities, maintenance, and outstanding items. The findings will be provided in a future status report following the issuance of the report.

i An inspection of containment integrity was performed and combined inspection report 50-277/87-19; 50-278/87-19 was issued on July 6,1987. The inspection was performed by Dr. J. Chung on June 1-5, 1987 and no violations were observed.

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0FFICIAL RECORD COPY 616 LINVILLE 7/17/87 - 0004.0.0 07/21/87

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