ML20245E656
| ML20245E656 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/22/1989 |
| From: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8906270360 | |
| Download: ML20245E656 (6) | |
Text
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.i 9CS i
JUN % 41989' l
1 Docket No. 50-293
,1 MEMORANDUM.FOR:
James T. Wiggins,. Chief Reactor. Projects Branch No. '3
' Division of Reactor Projects i
FROM:
A.' Randy Blough, Chief
.f Reactor Projects;Section No. 3B Division'of.Rea'ctor Projects
SUBJECT:
PILGRIM STATUS REPORT FOR THE PERIOD JUNE 3 - 16, 1989 Enclosed is the Pilgrim bi-weekly status report from the NRC Resident Offise at Pilgrim. The NRC-Restart Staf f is in place and was on-site monitoring licensee activities on an extended shift' basis during this report period.
The Pilgrim bi-weekly status report is intended to provide NRC management and the public with an overview of plant activities and NRC restart inspection activities.. Subsequent inspection reports will. address many of these topics-in more detail.
MI$310d Gy' A. Randy Blough, Chief Reactor Projects Section No. -3B Division of Reactor Projects
Enclosure:
As. stated OFFICIAL RECORD COPY NRCRI PILPC 0087/ARISTIA - 0301.0.0.
11/29/80
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. s Memorandum for James.T; Wiggins 2
l-cc w/ enc 1:
R. Bird, Senior Vice' President.-' Nuclear
'L. Gustin, Vice' President. Corporate Relations K. Highfill, Station Director.
R. Ar.derson, Plant Manager.
J.-~Dietrich, Licensing Division Manager-E. Robinson,. Nuclear Information Manager R. Swanson, Nuclear Engineering Department Manager The Honorable Edward M. Kennedy The Honorable Edward J.Markey.
.The Honorable Edward P. Kirby The Honorable Peter V. Forman Chairman, Board of Selectmen, ' Plymouth Chairman, Board of Selectmen, Carver Chairman, Board of Selectmen, Duxbury Chairman, Board of Selectmen, Marshfield Chairman, Board of Selectmen, Kingston Chairman, Board of Selectmen, Bridgewater Mayor, City of Taunton Plymouth Civil Defense Director P. Agnes, Assistant Secretary of Public Safety, Commonwealth of Massachusetts M. Ernst, Committee on Energy, Commonwealth of Massachusetts S. Pollard,' Massachusetts Secretary of Energy Resources B. McIntyre, Chairman, Department of Public Utilities l
M. Johnson, Chairman, Duxbury Nuclear Committee R. Shimshak, MASSPIRG R. Boulay, Director, Massachusetts Civil Defense Agency and Office'of Emergency Preparedness M. Conyngham, Legislative Assistant
.y M. Jeka, Legislative Assistant K. Anderson, Legislative Assistant Duxbury CURE Public Document Room (PDR) i Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC) t NRC Resident Inspector Commonwealth of Massachusetts (2)
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Region I Docket Room (with concurrences)
J. Taylor, EDO J. Dyer, EDO T. Murley, NRR F. Miraglia, NRR J. Partlow, NRP.
S. Varga, NR.C J. Roe, NRR l'. Perkins, NRR D. Crutchfield, NRR C. Rocsi, NRR F. Congel, NRR L. Shao, NRR R. Wessman, NRR D. Mcdonald, NRR L. Whitney, NRR P. Boehnert, ACRS W. Russell, RI T. Martin, RI W. Kane, RI B. Boger, RI M. Knapp, RI S. Collins, RI J. Durr, RI R. Gallo, RI R. Bellamy, RI W. Lazarus, RI P. Eapen, RI R. Blough, RI J. Lyash, RI M. Kohl, RI i
M. J. DiDonato, RI (2)
K. Abraham, RI (2)
M. Miller, RI C. Warren, Pilgrim T. Kim, Pilgrim C. Carpenter, Pilgrim
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0FFICIAL RECORD COPY NRCRI PILPC 0087/ARISTIA - 0003.0.0
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. Enclosure Pilgrim Status Report for the Period June 3 - 16, 1989 1.0 Plant Status As of 8:00 a.m. on June 16, 1989, the reactor was operating at approximately 25% power with the turbine generator synchronized to the grid.
2.0 Power Ascension Test Program Status The licensee has completed the original: scope of the Power Ascension Test Program up to the 25% power plateau.
Prior to continuation of the power 1 ascension program to the 50?s power' plateau, the licensee must obtain the NRC. Region I Regional Administrator's concurrence.. The program includes NRC approval points at 5%, 25?s, 50?! and 75% of full power and both a l
licensee written report and NRC review after. completion of testing at -
q full power.
The NRC Restart Assessment Panel will recommend to the Regional Administrator when the plant is considered ready to be released from each approval point.
3.0 Facilities Operations Summa n As reported in the last Pilgrim Status Report (May 20 - June 2,1989),
the plant was operating at approximately 25% power at the beginning of this report period.
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i At 12:05 p.m. on June 12, 1989, the licensee commenced a controlled reactor shutdown for a planned outage in. order to perform minor-I modifications, maintenance and testing.
The primary reason for the.
outage was to install output signal dampening devices (capacitors) on.the main steam line high flow Rosemount transmitters.. Detailed NRC review of this modification will be documented in NRC Inspection Report No.
50-293/89-07.
i At' 2:17 p.m. on June 15, 1989, the licensee brought the reactor critical.
The turbine generator was synchronized to.the electrical power distribution grid at 2:20 a.m. on June 16, 1989. The plant was returned j
to about 25% power while the licensee awaits release from the third NRC Approval Point (25% to 50% power). The licensee continued to conduct routine surveillance along with preventive and corrective maintenance throughout the period.
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l OFF[CIAL RECORD COPY NRCRI PILPC 0087/ARISTIA - 0004.0.0 11/29/80 l
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4.0 Items of Special Interest NRC Restart Assessment Penel An NRC Restart Assessment Panel meeting was held on June 8, 1989 at the NRC Region I Office in King of Prussia, Pennsylvania.
The Panel received a presentation from the licensee on their assessment of the results of the 5% to 25% Power Ascension Program, including their assessment of the April 12, 1989 Reactor Core Isolation Cooling (RCIC) system overpressurization event and the May 3, 1989 turbine trip / reactor scram.
The Restart Panel also was reviewing plant readiness to proceed up to 50%
power.
gg An NRC Restart Assessment Panel teleconference was held on June 15, 1989 at the NRC Region I Office in King of Prussia, Pennsylvania.
NRC management from Region I, the Office of Nuclear Reactor Regulation (NRR) and the NRC resident staff participated.
The Panel meets periodically to coordinate planning and execution of NRC inspection and licensing activities related to Pilgrim. The panel is chaired by Mr. Samuel J.
Collins, Deputy Director, Division of Reactor Projects, NRC Region I.
5.0 Emergency Notification System (ENS) Reports Inoperable Area Temperature Switch On June 9,1989 while the licensee was conducting a routine periodic surveillance on the Reactor Core Isolation Cooling (RCIC) system, stripped threads were discovered on a RCIC system area temperature switch terminal block.
The associated lead from an area temperature detector had been lifted and taped.
The licensee determined that the lead had been lifted and taped during the prior surveillance on May 14, 1989. The licensee subsequently replaced the terminal block and returned RCIC system to operable status.
The affected temperature detector was one of several redundant methods to determine the presence of a steam leak.
Inadvertent Reactor Scram While in Cold Shutdown On June 14, 1989 an inadvertent reactor scram signal was received while an operator was resetting a manual reactor scram which had been inserted to support maintenance. The inadvertent scram occurred when the reactor operator returned the scram discharge volume (SDV) high level scram -
bypass switch to " normal" position while a SDV high level alarm existed.
The scram discharge volume receives and contains water discharged from all associated hydraulic control units during a reactor scram.
Since the plant was in cold shutdown at the time, no rod movement occurred.
OFFICIAL RECORD COPY NRCRI PILPC 0087/ARISTIA - 0005.0.0 11/29/80
Reactor Water Cleanup System Isolation On June 15, 1989, the licensee experienced an isolation of the Reactor Water Cleanup (RWCU) system.
The RWCU system removes dissolved impurities and corrosion products from the reactor coolant. The isolation occurred during plant startup and was caused by a false indication of high system flow due to trapped air in the instrument lines.
Detailed NRC review of the above events and licensee actions will be documented in NRC Inspection Report No. 50-293/89-07.
6.C Pilgrim Restart Staff Activities l
The Pilgrim Restart Staff was in extended shift coverage throughout this report period. Additional personnel from NRC Region I, NRR and an NRC contractor were onsite during the report period to augment the resident inspection staff.
f A NRC-developed inspection plan addressing the 5-25% power plateau and the primary functional areas of operations, maintenance, surveillance, and startup testing continued to be impleinented.
The inspectors assessed operator performance, organizational interfaces, adherence to procedures and Technical Specification compliance.
The Pilgrim Restart Staff continued to evaluate the performance of i
licensee personnel and the plant to determine whether the licensee should be permitted to proceed to the next NRC approval point, 50% of rated power.
On June 9, NRC Region I issued NRC Inspection Report No. 50-298/89-05, which details NRC restart staff inspections during the period of March 11 - April 10,1989. This report will be available in the Local Public Document Room. The inspection noted generally good licensee performance.
Contact with the press and public continued throughout the period. The NRC Restart Manager and the Region I Public Affairs Officer have been handling inquiries from the press and the public.
Pilgrim Restart Staff Composition During Period The Pilgrim Restart Staff on-site was comprised of the following personnel during the period.
C. Warren, Senior Resident Inspector and Restart Manager T. Kim, Resident Inspector C. Carpenter, Resident Inspector J. Golla, Reactor Engineer, RI L. Zerr, Project Engineer, NRR G. Bethke, NRC Contractor M. Good, NRC Contractor Also onsite on June 2 and 5,1989 was Mr. A. Randy Blough, Chief, Reactor l
Projects Section 38.
OFFICIAL RECORD COPY NRCRI PILPC 0087/ARISTIA - 0006.0.0
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