IR 07100120/2012003

Forwards Plant Status Rept for 871120-1203.Three Resident Inspectors Monitored Activities at Plant During Rept Period

ML20237A343
Person / Time
Site:	Peach Bottom, 07100120
Issue date:	12/09/1987
From:	Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8712140417
Download: ML20237A343 (5)

Text

___________ _ _-____ _____ _ _ - __

..

09 DEC 1987 Docket No MEMORANDUM FOR: William F. Kane, Director, Division of Reactor Projects FROM: J. C. Linville, Chief, Reactor Projects Section 2A SUBJECT: PEACH BOTTOM ATOMIC POWER STATION STATUS REPORT FOR THE PERIOD November 20 - December 3, 1987 Enclosed is the Peach Bottom periodic status report from the NRC Resident Office at Peach Bottom. Three NRC resident inspectors monitored activities at the plant during the report perio These status reports are intended to provide NRC management and the public with an overview of plant activities.and NRC inspection activitie Subsequent inspection reports will address many of these topics in more detai '

[h$t5Lubisignv7gg James C. Linville, Chief Reactor Projects Section 2A Enclosure: As Stated kk

p 0FFICIAL RECORD COPY PB STATUS RPT 11/20-12/3 - 0001.0.0 ,

12/07/87  !

l ) l

._ - - - -

_ -

__ . _ _ _ _ _ - _____

-.

'

'

. William F. Kanc- 2 09 DEC 1987 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 .

Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)

Raymond L. Hovis, Esquire Thomas Magette, Power Plant Siting, Nuclear Evaluations W. M. Alden, Engineer in Charge, Licensing Sectio .

Doris Poulsen, Secretary of Harford County Council Public Document Room (PDR)

Local'Public Document Room (LPOR)

Nuclear Safety Information Center (NSIC) ,

NRC Resident-Inspector i Commonwealth of Pennsylvania i

bec w/encls:

Region I Docket Room (with concurrences)

J. Taylor, EDO T. Murley, NRR

.

i R. Starostecki, NRR  ;

F. Miraglia,'NRR 1 S. Varga, NRR 8.'Boyer, NRR )

W. Butler, NRR R. Martin, NRR W. Russell, RI W. Johnston, RI

.T. Martin, RI S. Collins, RI R. Gallo, RI K. Abraham, RI M. Miller, RI J. Williams, RI L. Scholl, RI B. Clayton, ED0

/ .

-

l R :DN RI'DRP Dh ) \

er# 1(f

'

Sc 611/rh1 Linville

)/ 87 12/I/87 12/8/87

'0FFICIAL RECORD COPY PB STATUS RPT 11/20-12/3 - 0002. /07/87 L-. . . . - - .- -------------_--_-_-_--___J

- _ - _ - _ _ _ _ _

.

ga-

'

William F. Kane 3 ENCLOSURE PEACH BOTTOM ATCMIC POWER STATION STATUS REPORT FOR THE PERIOD November 20 - December 3, 1987 1.0 Plant Status As of 8:00 a.m. on December 3, 1987, Unit 2 and 3 are in a cold condition per the March 31, 1987, NRC Order with coolant temperatures less than 200 degrees Fahrenheit. The Unit 3 core is completely off loaded into the spent fuel poo .0 Facility Operations Summary Unit 2 is completing a refueling outage which began March 13, 198 Final work is being performed to support the reactor pressure vessel hydrostatic test. Unit 3 has been in a cold condition per the March 31, 1987, NRC Order since April 1, 1987. The Unit 3 recirculation system pipe replacement outage is in progress. Piping decontamination flushes are in progress The vessel draindown was completed on December 1, 198 .0 Items of Special Interest 3.1 A meeting was held at Peach Bottom on November 20, 1987, to discuss the licensee's reorganization plans and restart plan submittals, 3.2 The licensee submitted their " Plan for Restart of Peach Bottom Atomic Power Station, Section 1, Corporate Action" on November 25, 1987. NRC review of this document is progressin .3 A meeting of the Advisory Committee on Reactor Safeguards was held on December 3, 1987, to discuss Peach Botto .0 Other Items of Interest 4.1 The licensee made an Emergency Notification System (ENS) call on November 23, 1987, to report a loss of emergency assessment capability for 31 minute The off site power supply to the Technical Support Center (TSC) and Emergency Operations Facility (E0F) tripped. The operating shift was unable to start the Unit 1 diesel generator (DG) to supply power to the TSC/ EOF because the DG was out of service due to modification activities.

l 4.2 On November 29, 1987, a group II A reactor water cleanup (RWCU)

isolation occurred on high temperature of 200 degrees F. No valve l movement occurred because the RWCU system was isolated for a decon-l tamination (decon) flush. However, since the isol; tion logic de-l energized, the licensee made an ENS call. The cause of the high I temperature RWCU isolation was an actual decon solution temperature I

. _ _ _ _ _ - _. _ _ _ . ____ _ _ _-____ __ _ ____ ___-____

.  !

.

'

William F. Kane '4 of 190 degrees F during the solution circulation phase. Special procedures implemented for this did not provide a step to bypass the  ;

high temperature isolation signal. The licensee revised the SPs and  !

, continued with the flush.

l 4.3 On November 30, 1987, a Unit 3 watchman left her post without a warning or a proper relie She had been at this post for about three hours and had requested a relief using profanity on the radi The relief watchman arrived at the post and discovered it unattende The post orders and radio were there, hawever. A check of the security computer determined that the watchman left the protected area, and her security badge was found at the egress station. Her employment has been terminated. A corporal of the guards had checked this post an hour before the discovery that it was unoccupied with no abnormalities noted. A search of the area was delayed due to high radiation levels from reactor vessel draindown. The licensee made an ENS call. Subsequent drywell inspection on' December 1, 1987, found no abnormalitie .4 On December 2, 1987, an outboard Group III isolation occurred on Unit 2. Various ventilation valves closed, various ventilation fans q tripped, and the "B" Standby Gas Treatment System (SGTS) fan starte The "B" SGTS train inlet and outlet Valves did not open because the train was tagged out of service. All systems functioned as designed for the one-half isolation. The cause of the isolation was a blown fuse to an isolation logic rela Initial licensee investigation I suggests that the cause of'the blown fuse was due to a modification

{

acceptance test to revise the logic of the automatic depressurization '

system. The fuse was replaced, the isolation was reset, and an ENS call was mad Further licensee investigation is continuing to determine the exact cause of the blown fus .5 On December 2, 1987, it was determined that the new security computer had lost trace history on access card The licensee had replaced the security computer with a better system with a larger storage capacity on November 22, 1987. During the changeover, a command to increase the memory block was omitted which lead to the computer default to a smaller memory size. From the switchover of computers on November 22 to December 2, 1987, a large block of trace history was lost. The licensee took immediate corrective action by expanding the memory block to the required configuration and made an ENS call .

The licensee is investigating this event to determine the cause of failure to provide the software with the proper comman The resident inspectors are following the licensee's investigations and corrective actions regarding these occurrence _ . _ _ _ _ _ _ _ _ _ _ .

_ _ _ _ . _ _ - _ _ - _ - - - _ - _ -

> e

.

'

William F. Kane 5 5.0 NRC Activities During the Perio Three NRC Resident Inspectors were assigned to monitor plant activities between November 20 and Decenber 3,1987. These individuals consisted of the following:

Thomas P. Johnson - Senior Resident Inspector Richard J. Urban - Resident Inspector Larry E. Myers - Resident Inspector Areas inspected included operational safety, shutdown order commitments, radiation protection, physical security, control room activities and demeanor, reportable events, surveillance testing, outage activities, maintenance, and outstanding item NRC Combined Inspection Report 50-277/87-20 and 50-278/87-2C was issued on November 24, 1987. The inspection was a review of the licensee's security and safeguards program during the period June 29 - Jsly 2, 198 No violations were note (

,

_ _ _ _ _ _ _ - - _