ML20215L887

Forwards Biweekly Status Rept for 861009-22.Current SALP Period Extended to 870431

ML20215L887
Person / Time
Site:	Pilgrim
Issue date:	10/24/1986
From:	Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8610290345
Download: ML20215L887 (5)

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24 OCT 1986 Docket No. 50-293 MEMORANDUM FOR: Harry Kister, Chief Projects Branch No. 1 FROM: Jack R. Strosnider, Chief Reactor Projects Section IB

SUBJECT:

PILGilIM STATUS REPORT FOR THE PERIOD OCTOBER 9, 1986 -

OCTOBER 22, 1986 Enclosed is the bi-weekly status report from the NRC Resident Office at Pilgrim.

Two NRC Resident Inspectors monitored routine activities at the plant during the report period. In addition one region based inspector and a six-member inspection team were onsite during portions of the period. The reactor re-mained in cold shutdown throughout the period for maintenance.

The NRC has announced that the current Systematic Assessment of Licensee Perfor-mance (SALP) period will be extended by six months. The assessment period which started on November 1, 1985 will now end on April 31, 1987.

These status reports are intended to provide NRC management and the public with an overview of plant activities and NRC inspection activities. Subsequent in-spection reports will address many of these topics in more detail.

Jack R. Strosnider, Chief Reactor Projects Section IB I

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I OFFICIAL RECORD COPY PILGRIM STATUS RPT - 0001.0.0 8610290345 061024 gDR ADOCK 05000293 PDR

Harry B. Kister 2 m

cc w/ enc 1:

T. Murley, NRC, RI W. Kane, RI S. Ebneter, NRC, RI T. Martin, RI J. Partlow, NRC, IE S. Collins, RI J. Zwolinski, NRC, NRR J. Lydon, Chief Operating Officer, BECO L. Oxsen, Vice President, Nuclear Operations, BECO A. Pedersen, Station Manager, BECO Paul Levy, Chairman, Department of Public Utilities Chairman, Board of Selectmen J. D. Keyes R. Bowlay Plymouth Civil Defense Director Senator Edward P. Kirby Representative Peter Forman S. M. Pollard M. Conyngham M. R. Jeka K. R. Anderson The Honorable E. J. Markey Public Document Room )PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Massachusetts (2) bec w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

DRP Section Chief W. Raymond, SRI, Vermont Yankee T. Shediosky, SRI Millstone 1&2 H. Eichenholz, SRI, Yankee P. Leech, LPM, NRR PA0 (2)

RI:DRP RI:DRP RT

McBride K" (Strosnider 10/14/86 10/14/86 10 86 0FFICIAL RECORD COPY PILGRIM STATUS RPT - 0002.0.0 11/29/80

4 ENCLOSURE PILGRIM STATUS REPORT FOR THE PERIOD OCTOBER 9 - OCTOBER 22, 1986 1.0 Plant Status As of 8:00 a.m. on October 22, 1986, the reactor was in cold shutdown with reactor coolant temperature at about 110 degrees Fahrenheit.

2.0 Facility Operations Summary The plant has been shut down for maintenance, and to make program improvements since April 12, 1986. Boston Edison announced on July 25, 1986 that the present outage will continue until April 1987 and will include refueling of the reactor.

3.0 Items of Special Interest Systematic Assessment of Licensee Performance (SALP) Evaluation Period Change The NRC: Region I has announced that the evaluation period for the next Pilgrim SALP will extend 18 months, from November 1, 1985 to April 30, 1987. The period was initially scheduled to end October 31, 1986. The SALP process evaluates the licensee's performance, progress and management effectiveness over a period of time, usually one year to eighteen months.

This revision will allow for a more meaningful evaluation of Boston Edison's performance including the effectiveness of recently implemented initiatives.

Residual Heat Removal (RHR) Pump Inspection Results Inspection of the "A" RHR pump has identified signs of pump impeller and shaft overheating and damage. In addition, the "A" RHR pump casing was found to be distorted, also apparently as a result of overheating. Per-formance test results on the damage "A" RHR pump prior to its disassembly demonstrated that the pump was able to operate and perform its safety func-tion. The RHR system provides cooling of the reactor and primary contain-l ment during normal plant operation and shutdown conditions. Under accident conditions the system provides an emergency source of cooling water to the reactor vessel. Performance testing of these pumps is routinely performed on a monthly basis. The licensee is evaluating possible causes for the

! damage. The pump will be repaired prior to reassembly. The other three c RHR pumps had been previously disassembled during this outage. No j significant damage was found in those pumps.

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OFFICIAL RECORD COPY PILGRIM STATUS RPT - 0003.0.0 l 11/29/80 l

Harry B. Kister 2 Inservice Inspection Program Results The licensee is performing an extensive inservice inspection (ISI) program.

As part of this ISI program, nondestructive examinations of numerous reac-tor coolant system welds are conducted. The purpose of these examinations is to identify any early sign of pipe or weld cracking. Indications of flaws in or around the welds are documented and evaluated to determine possible cause and effects.

Five main steam line flaw indications were identified during the previous report period. During this period four additional weld flaw indications were identified by the licensee on other systems. The flaw indications are one inch or less in length and do not pose an immediate concern re-garding piping integrity. The licensee reported discovery of the indica-tions to the NRC via the ENS on October 18, 1986. The inspectors will review the licensee's evaluation of these indications, and any repairs needed.

Disconnected Reactor Protection System Wiring On October 17, 1986 the licensee notified the NRC via the Emergency Notification System (ENS) that a Reactor Protection System (RPS) wire was found disconnected. The wire had pulled free of the device used to attach it in the control panel. The function of the RPS is to deenergize if off normal conditions are sensed, causing the reactor to shut down. The effect of the disconnected wire was to deenergize a portion of the RPS system. In this condition the affected portion was " Failed-safe" in that if the reactor had been in operation a partial reactor shutdown signal would have resulted.

The licensee is evaluating possible causes for the disconnected wire.

NRC Special Team Inspection A six member NRC inspection team arrived onsite October 20, 1986 and will remain on site through October 24, 1986. Boston Edison, under a 1984 order from the NRC, implemented a radiological improvement plan. The purpose of this special team inspection is to evaluate the effectiveness of improve-ments made to licensee's radiation protection program. A routine inspection report will be issued, describing the team's findings.

l 4.0 NRC Staff Status During the Period i

Two NRC Resident Inspectors monitored plant activities between October 9, and October 22, 1986. The resident inspector staff at Pilgrim during the report period consists of the following:

Martin McBride, Ph.D. --- Senior Resident Inspector Jeffrey Lyash --- Resident Inspector l

l l 0FFICIAL RECORD COPY PILGRIM STATUS RPT - 0004.0.0 l

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Harry B. Kister 3 In addition to the special team inspection described above, one NRC specialist inspector arrived on site October 20, 1986. The purpose of the inspection is to evaluate the effectiveness of the licensee's fire protection program. This inspection will conclude on October 24, 1986.

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OFFICIAL RECORD COPY PILGRIM STATUS RPT - 0005.0.0 11/29/80

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