ML20212L304
| ML20212L304 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/27/1987 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Capra R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8703100344 | |
| Download: ML20212L304 (4) | |
Text
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FEB 2 71987 i
I Docket No. 50-293 t
I MEMORANDUM FOR:
Robert A. Capra, Acting Chief, i
Reactor Projects Branch 1 FROM:
James T. Wiggins, Chief i
Reactor Projects Section IB
SUBJECT:
PILGRIM STATUS REPORT FOR THE PERIOD FEBRUARY 12 -
FEBRUARY 25, 1987 i
Enclosed is the Pilgrim bi-weekly status report from the NRC Resident Office at Pilgrim. Three NRC resident inspectors, several region-based inspectors and one visiting senior resident inspector monitored activities at the plant during the report period. The licensee completed defueling on February 13, 1987 to support performance of certain plant modifications and inservice i
inspection on the reactor vessel.
l These status reports are intended to provide NRC management and the pubite with an overview of plant activities and NRC inspection activities.
Subsequent inspection reports will address many of these topics in more
- detail, l
Or161M1UlPCA378 l
l James T. Wiggins, Chief Reactor Projects Section IB 1
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OFFICIAL RECORD COPY PILGRIM WEEKLY STATUS REPORT -
l 11/29/80 I
'f E 5 l
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f cc w/encI:
T. Murley, NRC, RI
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W. Kane, RI i
S. Ebneter, NRC, RI T. Martin, RI l
J. Partlow, NRC, IE l
S. Collins, RI H. Denton, NRC, NRR l
J. Zwolinski, NRC, NRR R. Auluck, NRC, NRR J. Lydon, Chief Operating Officer, BECO R. Bird, Senior Vice President-Nuclear-l L. Oxsen, Vice President, Nuclear Operations, BECO K. Roberts, Station Manager, BECO Paul Levy, Chairman, Department of Public Utilities Chairman, Board of Selectmen J. D. Keyes l
R. Bowlay l
Plymouth Civil Defense Director Senator Edward P. Kirby l
Representative Peter Forman l
S. M. Pollard N. Conyngham M. R. Joka K. R. Anderson The Honorable E. J. Markey i
Pubite Document Room (PDR)
I Local Public Document Room (LPDR) l Nuclear Safety Information Center (NSIC) l l
NRC Resident Inspec'.or l
Comn$ wealth of Massachusetts (2) bec w/ encl:
Region!DocketRoom(withconcurrences)
Management Assistant, DRMA (w/o encI)
DRP Section Chief R. Auluck, LPM, NRR PA0 (2) l l
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TJ. W'p/ aig Dategjgyo l
M. Mc t
R capra Date ate I
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ENCLOSURE PILGRIM STATUS rep 0RT FOR THE PERIOD FEBRUARY 12. - FEBRUARY 25. 1987 1.0 Plant Status As of 8:00 a.m. on February 25, 1987, moderator temperature was about 70 degrees Fahrenheit. All fuel has been removed from the reactor vessel and transferred to the spent fuel pool.
2.0 Facility Operations Summary The plant has been shut down for maintenance, and to make program improvements since April 12, 1986.
The present outage is presently scheduled to continue until June 1987.
The licensee conducted reactor defueling between February 6 - February 13, 1987 to perform plant modifications and inservice inspections involving the reactor vessel and its components. All 580 fuel assemblies have been transferred from the reactor vessel to the spent fuel pool.
Other major ongoing modification and maintenance projects include: 1) diesel generator overhaul, 2) control rod drive replacement, 3) reactor vessel level instrument reference Icg replacement, 4) inservice inspection of steam turbines and 5) preventive maintenances on electrical buses and breakers.
Fuel reload is scheduled to begin in approximately two months.
3.0 Emergency Notification System (ENS) Reports During this period, the licensee made two reports to NRC pursuant to 10 CFR 50.72. These reports described the following incidents:
A.
On February 11, 1987, the licensee reported that the two of four Main Steam Safety Relief Valves (SRV) had failed the lift pressure tests. One valve lifted 1.4 percent above destrq set point and a second valve lifted 2.2 percent below design.
Technical Specifications require settings to be within plus or minus one percent of nominal set point.
The licensee is in the process of refurbishing the valves.
The valves will be retested before reinstallation.
D.
On February 19, 1987 the licensee discovered that the fixed dry chemical fire suppression system for the "A" Emergency Ofesel Generator may have been inoperable since December 23, 1986. A maintenance request (MR) written on December 23, 1986 documented that the pressure in one of three chemical storage bottles associated with the system was found to be 270 psi rather than the required minimum 275 psi.
OFFICIAL RECORD COPY PILGRIM WEEKLY STATUS REPORT -
11/29/80
Upon discovery of the problem on February 19 the licensee estabitshed a continuous fire watch in the area. While no i
continuous fire watch was in place from December 23, 1986 to February 19, 1987 a roving fire patrol toured the area on an hourly basis.
4.0 NRC Staff Status During the Period Three NRC Resident Inspectors monitored plant activities between February 12, and February 25, 1987. The inspection staff at Pilgrim during the report period consisted of the following:
Martin McBride, Ph.D. --- Senior Resident Inspector Jeffrey Lyash
--- Resident Inspector Tae Kim
--- Resident Inspector Eight NRC specialist inspectors were also onsite during the period.
Areas examined by the inspectors included:
- 1) ongoing modifications, 2) the onsite worker radiation protection program, 3) the station maintenance program, 4) Post Accident Sampling System, and 5) followup on previous NRC identified issues.
In addition, the senior resident inspector from the Susquehanna facility assisted the resident inspectors i
during the week of February 23, 1987.
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